Ad - j NUREG/IA-0156

Vol. 3

IPSN 99/08-3

NSI RRC 2179 .. 3

international

Agreement Report

Data Base on the Behavior of High Burnup Fuel Rods

with Zr-1%Nb Cladding and U0 2 Fuel (VVER Type)

under Reactivity Accident Conditions

Test and Calculation Results

Prepared by

L Ycgorova, G. Abyshov, V. Malofeev, A. Awakumov, E. Kaplar, K. Lioutov, A. Shestopalov, A. Konobeyev,

N. Jouravkova

Nuclear Safety Institute of Russian Research Centre "Kurchatov Institute"

Kurchatov Square 1, Moscow 123182, Russia

A. Bortash, M. Kalugin, A. Zvyageen, K. Mikitiouk

Institute of Nuclear Reactors of Russian Research Centre 'Kurchatov Institute"

Kurchatov Square 1, Moscow 123182, Russia

V. Smirnov, A. Goryachev, V. Prokhorov, Yu. Kosvintsev, 0. Makarov

State Research Centre "Research Institute of Atomic Reactors'

Dimitrovgrad 433510, Russia

V. Pakhnitz, A. Vurim

Institute of Atomic Energy of National Nuclear Centre of Kazakhstan Republic

Semipalatinsk 490021, Kazakhstan

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, DC 20555-0001

July 1999

Prepared for

U.S. Nuclear Regulatory Commission, Institute for Protection and Nuclear Safety (France) and

Minisnry of Science and Technologies of Russian Federation

Published by

U.S. Nuclear Regulatory Commission
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ABSTRACT

Test and calculation results characterizing the behavior of fuel rods of the VVER type with Zr-1%Nb cladding and

U02 fuel under reactivity accident conditions are presented in this volume of report. The data base includes the

following characteristics:

* some parameters of commercial fuel elements of VVER-1000 type before and after irradiation, parameters of

fuel cycles of fuel elements irradiated at the Unit 5 of NovoVoronezh nuclear power plant (NV NPP);

* test parameters of fuel rods before, during and after the reactivity-initiated-accident (RIA) tests

* neutronic and thermomechanical parameters of fuel rods during RIA tests calculated by different computer

codes;

* measured mechanical properties of the Zr-I%Nb cladding obtained with special tests;

* parameters of the Zr-I %Nb cladding failure of the ballooning type measured under the burst test conditions.

iii

TABLE OF CONTENTS

Page

1. EXECUTIVE SUMMARY ........................... ........................

2. GUIDE TO THE DATA BASE ........................... .** .................... 2

2.1. COMMENTS TO APPENDIX A ............................... 2

2.2. COMMENTS TO APPENDIX B ........................... 2; 2

2.3. COMMENTS TO APPENDIXES C, D, E ............................ 3

2.4. COMMENTS TO APPENDIX F ............................ 3

2.5. COMMENTS TO APPENDIX G ............................ 3

2.6. COMMENTS TO APPENDIXES H, I ............................ 6

2.7. COMMENTS TO APPENDIX J ............................ 6

2.8. COMMENTS TO APPENDIX K ............................ 6

v

LIST OF APPENDIXES

APPENDIX A

APPENDIX B

APPENDIX C

APPENDIX C-I

APPENDIX C-2

APPENDIX C-3

APPENDIX C4

APPENDIX C-5

APPENDIX C-6

APPENDIX C-7

APPENDIX C-8

APPENDIX C-9

APPENDIX C-10

APPENDIX C-li

APPENDIX C-12

APPENDIX C-13

APPENDIX D

APPENDIX D-l

APPENDIX D-2

APPENDIX D-3

APPENDIX D4

APPENDIX D-5

APPENDIX D-6

APPENDIX D-7

APPENDIX D-8

APPENDIX D-9

APPENDIX D-10

APPENDIX E

APPENDIX E-l

APPENDIX E-2

APPENDIXF

Typical Characteristics of WVER-1000 Fuel Rods before the Irradiation

at NV NPP

Characteristics of NV NPP Power Operation and Commercial Fuel

Rods after the Irradiation

Initial Characteristics of Refabricated Fuel Rods

(Preirradiated Fuel, Preirradiated Cladding)

Initial Individual Characteristics for Fuel Rod #HIT

Initial Individual Characteristics for Fuel Rod #H2T

Initial Individual Characteristics for Fuel Rod #H3T

Initial Individual Characteristics for Fuel Rod #H4T

Initial Individual Characteristics for Fuel Rod #H5T

Initial Individual Characteristics for Fuel Rod #H6T

Initial Individual Characteristics for Fuel Rod #H7T

Initial Individual Characteristics for Fuel Rod #H8T

Initial Individual Characteristics for Fuel Rod #B9T

Initial Individual Characteristics for Fuel Rod #B OT

Initial Individual Characteristics for Fuel Rod #BIIT

Initial Individual Characteristicsfor Fuel Rod #BI2T

Initial Individual Characteristics for Fuel Rod #B13T

Initial Characteristics of Refabricated Fuel Rods

(Fresh Fuel, Preirradiated Cladding)

Initial Individual Characteristics for Fuel Rod #HJ4T

Initial Individual Characteristics for Fuel Rod #HIST

Initial Individual Characteristics for Fuel Rod #HJ6T

Initial Individual Characteristics for Fuel Rod #H67T

Initial Individual Characteristics for Fuel Rod #HI8T

Initial Individual Characteristics for Fuel Rod #BI9T

Initial Individual Characteristics for Fuel Rod #BMOT

Initial Individual Characteristics for Fuel Rod #21 T

Initial Individual Characteristics for Fuel Rod #B22T

Initial Individual Characteristicsfor Fuel Rod #B23T

Initial Characteristics of Fresh Fuel Rods

Initial Individual Characteristics for Fuel Rod #H6C

Initial Individual Characteristics for Fuel Rod #B20C

Characteristics of IGR Reactor Tests

Page

A-1

B-1

C-1

C-9

C-19

C-29

C-39

C-49

C-59

C-69

C-79

C-89

C-99

C-109

C-119

C-129

D-1

D-9

D-13

D-17

D-21

D-25

D-29

D-33

D-37

D41

D45

E-1

E-7

E-ll

F-1

Vii
LIST OF APPENDIXES (CONTD.)

APPENDIX G

APPENDIX G-1

APPENDIX G-2

APPENDIX G-3

APPENDIX G4

APPENDIX G-5

APPENDIX G-6

APPENDIX G-7

APPENDIX G-8

APPENDIX G-9

APPENDIX G-10

APPENDIX G-11

APPENDIX G-12

APPENDIX G-13

APPENDIX H

APPENDIX H-I

APPENDIX H-2

APPENDIX H-3

APPENDIX H-4

APPENDIX H-5

APPENDIX H-6

APPENDIX H-7

APPENDIX H-8

APPENDIX H-9

APPENDIX H-10

APPENDIX I

APPENDIX I-i

APPENDIX i-2

APPENDIX J

APPENDIX K

Measured and Calculated Characteristics of Refabricated Fuel Rods

(Preirradiated Fuel, Preirradiated Cladding) during and after IGR

Reactor Tests

Individual Characteristicsfor Fuel Rod #HI T under IGR Test

Individual Characteristicsfor Fuel Rod #H2T under IGR Test

Individual Characteristicsfor Fuel Rod #H3T under IGR Test

Individual Characteristics for Fuel Rod #H4T under IGR Test

Individual Characteristics for Fuel Rod #H5T under IGR Test

Individual Characteristics for Fuel Rod #H6T under IGR Test

Individual Characteristics for Fuel Rod #H7T under IGR Test

Individual Characteristics for Fuel Rod #H8T under IGR Test

Individual Characteristicsfor Fuel Rod #B9T under IGR Test

Individual Characteristics for Fuel Rod #BIOT under IGR Test

Individual Characteristicsfor Fuel Rod #BIITunder IGR Test

Individual Characteristics for Fuel Rod #B12T under lGR Test

Individual Characteristicsfor Fuel Rod #B13T under IGR Test

Characteristics of Refabricated Fuel Rods (Fresh Fuel, Preirradiated

Cladding) during and after IGR Reactor Tests

Individual Characteristics for Fuel Rod #H14T under IGR Test

Irdividual Characteristicsfor Fuel Rod #HIST under IGR Test

hzdividual Characteristics for Fuel Rod #H16T under IGR Test

Individual Characteristicsfor Fuel Rod #HI 7T under IGR Test

Individual Characteristicsfor Fuel Rod #H18T under IGR Test

Individual Characteristics for Fuel Rod #B19T under IGR Test

Individual Characteristics for Fuel Rod #B20T under IGR Test

Individual Characteristicsfor Fuel Rod #B21 T under IGR Test

Individual Characteristicsfor Fuel Rod #B22T under IGR Test

Individual Characteristics for Fuel Rod #B23T under IGR Test

Characteristics of Fresh Fuel Rods during and after IGR Reactor Tests

Individual Characteristics for Fuel Rod #1H6C under IGR Test

Individual Characteristics for Fuel Rod #B20C under IGR Test

Mechanical Properties of the Zr-1%Nb Cladding

Results of Tests to Measure the Parameters of the Zr-1%Nb Claddhig

Failure due to Ballooning

G-I

G-1

G-21

G-43

G-65

G-85

G-105

G-125

G-147

G-167

G-187

G-207

G-225

G-245

H-1

H-l

H-19

H-37

H-55

H-73

H-91

H-lll

H-129

H-149

H-169

I-1

1f1

1-19

J-1

K-1

viii
ACKNOWLEDGMENTS

An important contribution to the preparation of this volume of the report, including the conduct of calculations and

experimental studies, was made by the following specialists:

* Nuclear Safety Institute of RRC "Kurchatov Institute" (Moscow, Russia):

A. Degtyariov;

* Institute of Nuclear Reactors of RRC <<Kurchatov Institute> (Moscow, Russia):

A. Polismakov, D. Belov, P. Fomitchenko, V. Polvanov;

* Research Institute of Atomic Reactors (Dimitrovgrad, Russia):

L Stupina, L Zvir, V. Pimenov, V. Zhitelev;

* Institute of Atomic Energy of National Nuclear Center (Semipalatinsk, Kazakhstan):

S. Koltyshev, A. Levin.

ix

1. EXECUTIVE SUMMARY

This volume of the report contains a unique systematized set of data characterizing parameters of VVER fuel

elements before, during and after the basic irradiation at the NovoVoronezh nuclear power plant (NV NPP);

before, during and after tests under reactivity-initiated-accident (RIA) conditions; as well as original

mechanical properties of unirradiated and irradiated Zr-I%Nb claddings. The structural diagram of this data

base is presented in Fig. 1.1.

Parameters of commercial VVER-1OOO

fuel elements before irradiation at NV NPP

Parameters of commercial VVER

I cladding tubes and VVER fresh fuel I

I

Parameters of fuel cycles

at NV NPP

I:

l  I I I I I I1

Measured parameters

of high bumup fuel

rods refabricated

of commercial

VVER fuel elements

irradiated up lo

48 MWd/kgU

Measured parameters

of fuel rods %Nith

fresh fuel and

irradiated claddings

refabricated of

commercial fuel

elements

Measured

parameters

of fresh

VVER

fuel rods

Measured parameters

of ring tensile

specimens and tube

burst specimens

manufactured of

irradiated commercial

VVER claddings

Measured parameters

of ring tensile

specimens and tube

burst specimens

manufactured

of unirradiated

VVER tubes

4I I

I

Measured parametcrs Of specimens

after tensile and burst tests

Measured mechanical properties

and burst parameters of

Zr-l% Nb claddings

l

IMeasuredparameters of L

|IGR/RIA test conditions|

. - a. . . ., . a . -1 

Measured and calculated - parameters of VVER fuel -

rods during and after :

'IGR/RlAtests I-'-: .. . . , - , !j

Input data for FRAP-T6

and SCANAIR codes . - .

Fig. 1.1. Structure of the IGR/RIA data base

The data base, included into this volume, is composed in such a way that it is possible to use it having only

the information of Chapter 2 of this volume of the report.

1
2. GUIDE TO THE DATA BASE

Data base is composed of the following sequential set of the data base structural components concentrated in

Appendixes:

APPENDIX A

APPENDIX B

APPENDIX C

APPENDIX D

APPENDIX E

APPENDIX F

APPENDIX G

APPENDIX H

APPENDIX I

APPENDIX J

APPENDIX K

Typical Characteristics of VVER-1000 Fuel Rods before the Irradiation

at NV NPP

Characteristics of NV NPP Power Operation and Commercial Fuel Rods after the

Irradiation

Initial Characteristics of Refabricated Fuel Rods

(Preirradiated Fuel, Preirradiated Cladding)

Initial Characteristics of Refabricated Fuel Rods

(Fresh Fuel, Preirradiated Cladding)

Initial Characteristics of Fresh Fuel Rods

Characteristics of IGR Reactor Tests

Measured and Calculated Characteristics of Refabricated Fuel Rods

(Preirradiated Fuel, Preirradiated Cladding) during and after IGR Reactor Tests

Characteristics of Refabricated Fuel Rods (Fresh Fuel, Preirradiated Cladding)

during and after IGR Reactor Tests

Characteristics of Fresh Fuel Rods during and after IGR Reactor Tests

Mechanical Properties of the Zr-I%Nb Cladding

Results of Tests to Measure the Parameters of the Zr-I %Nb Cladding Failure due

to Ballooning

A-I

B-I

C-I

D-l

E-I

F-I

G-I

H-I

I-I

J-1

K-l

The comments necessary to work with the information presented in every Appendix are presented in the subsections

of this Chapter.

2.1. Comments to Appendix A

No special measurements were performed to determine parameters of VVER fuel elements that were used for the

manufacture of refabricated fuel rods for RIA tests. Therefore typical characteristics of standard VVER-1000 fuel

elements are presented in this Appendix. It is important to pay attention that the typical cladding outer diameter for

the VVER fuel element is 9.1 mm, while the outer diameter of the VVER cladding tube is 9.14 mm. This

discrepancy in dimensions is caused by the fact that the procedure of chemical etching of the cladding of fabricated

fuel elements is planned in the technological cycle. During this process the outer cladding diameter is decreased

from 9.14 to 9.1 mm.

2.2. Comments to Appendix B

But for the parameters of the fuel cycle, the set of specially measured characteristics is presented to characterize the

parameters of commercial fuel elements #317 and #22, which were used for the refabrication of fuel rods tested later

under IGR/RIA conditions. In some cases parameters of the fuel element # 307 are presented instead of the fuel

element #317. Fuel element #307 can be considered as a complete analogue of the fuel element #317. The

description of experimental procedures that were used to obtain this measured data base is presented in Chapters 2 -

4 of Volume 2 of this report.

2
2.3. Comments to Appendixes C, D, E

These Appendixes contain the data base to characterize parameters of the following three types of fuel rods

before IGR tests:

1. High burnup fuel rods (Appendix C);

2. Fuel rods with the irradiated cladding and the fresh fuel (Appendix D);

3. Fuel rods with the unirradiated cladding and the fresh fuel (Appendix E).

Thirteen high burnup fuel rods were manufactured by the refabrication of commercial fuel elements #317 and

#22. Ten fuel rods with irradiated claddings and the fresh fuel were fabricated of cladding parts of the

commercial fuel element #317 and fresh fuel pellets of the VVER-1OOO type. Two fresh fuel rods were

fabricated of the standard Zr-I%Nb cladding tube and fresh fuel pellets of the VVER-1000 type.

All three Appendixes contain:

measured representative parameters of fuel rods that characterize each type of fuel rods;

measured consolidated parameters, which characterize some design parameters, and parameters presented in

technical documents for each fuel rod;

the whole set of the r, z, t distribution of fuel rod individual parameters to characterize the isotopic

composition, burnup geometry, fuel mass, and free gas volume.

Description of procedures that were used to get those parameters is presented in Chapters 2 - 4 of Volume 2

of this report.

2.4. Comments to Appendix F

The data base presented in this Appendix characterizes such parameters of IGR/RIA test conditions as:

* type of the used coolant (air, water);

* pulse half width;

* measured power history and energy deposition history for each of the tested fuel rods.

It should be noted that actually measured signals of one ionization chamber located in IGR reactor are

presented in this Appendix to characterize the power history and the energy deposition history versus time for

each fuel rod, because these measured parameters were used as input data for further procedures.

2.5. Comments to Appendix G

In general this Appendix consists of thirteen independent Sub-appendixes, each of them containing a data

base to characterize individual parameters of each of the thirteen high burnup fuel rods during and after IGR

tests. It should be noted that <H>> letter in the designation of the fuel rod indicates that the fuel rod was tested

in the water coolant; accordingly, <B)> letter indicates that the air coolant was used. The individual data base

for each of high burnup fuel rods consists of experimental and calculated results. Calculated results were

obtained by FRAP-T6 and SCANAIR codes. The absence or interpolations of calculated results for one of the

codes or for both of them was caused by one of the following reasons:

* code does not contain models necessary to calculate a given parameter;

* code does not contain models necessary to calculate some parameters of the fuel rod, in this case the

calculation of other parameters becomes not expedient, as a big systematic error appears in the prediction

of them;

* calculated parameter has unbelievable fluctuations due to convergence problems.

Table 2.1 and Table 2.2 list a set of special comments to define the terminology used in this Appendix.

3
Table 2.1. Set of comments to terms used in tables of Appendix G to characterize test parameters of fuel rods

The used term Comments

1. Reactor energy deposition vs. Integral current of ionization chamber of IGR reactor at i-time

time (%) (gAs) ratio to the integral current of the ionization chamber at

infinite time (t=600 s)

2. Cumulative number of fissions in Total number of fissions for a given isotope which occurred by the

fuel rod vs. time (fiss) i-time within the whole mass of fuel

3. Power of fuel rod vs. time (kW) Power generated in the whole mass of the fuel rod at i-time. The

power was defined with consideration of the whole spectrum of

the irradiation from the reactor

4. Energy deposition in fuel rod vs. Energy absorbed in the whole mass of the fuel by i-time and

time (callg fuel) normalized for the fuel mass

5. Cumulative number of fissions at Total number of fissions of a given isotope that happened in the

axial interval (fiss) j-axial interval of the fuel column within 0- s

6. Maximum power of the fuel rod Axial profile of the maximum power value determined according

vs. axial coordinate (kW) to item 3.

7. Energy deposition at infinite time Total energy absorbed by the fuel mass in a given axial interval

vs. axial coordinate (callg fuel) within the time 0- s, normalized for the fuel mass in this interval

8. Number of fissions vs. radial fuel Total number of fissions of a given isotope with occurred in the

zone (fiss) undamaged part of the reviewed radial zone of the fuel column

within 0- s. Characteristics of the undamaged part are presented

in Appendix C.

9. Power of the fuel rod vs. radial Radial profile of the maximum power value determined according

fuel zone (kW) to item 3, and corrected in such a way that only the mass of the

undamaged part of fuel column was considered. Characteristics of

the undamaged part are presented in Appendix C.

10. Energy deposition vs. radial fuel Total energy absorbed in a given radial zone of the undamaged

zone (calg fuel) part of the fuel column normalized for the fuel mass of the

undamaged part of this radial zone. The time interval is 0- s

11. Energy deposition vs. radial fuel Energy deposition of a given radial zone of the undamaged part of

zone (per-unit) the fuel column normalized for a corresponding energy deposition

of the 4th radial zone

4
Table 2.2. Set of Comments to the terms used in tables of Appendix G to characterize fuel rod

parameters calculated by FRAP-T6 and SCANAIR codes

The used term Comments

1. Enthalpy at the fuel radius vs. time Fuel enthalpy vs. time in the point with a given radial and axial

(callg fuel) coordinates corresponding to the peak power for the power axial

distribution (Table 2.1 item 6)

2. Fuel enthalpy vs. time (calg fuel) Radially averaged fuel enthalpy versus time in the cross-section,

corresponding to the axial peak power (Table 2.1 item 6)

3. Energy deposition in fuel rod vs. Test input data for calculations (see Table 2.1 item 6)

time (callg fuel)

4: Energy deposition vs. time Calculations of all fuel rod parameters were performed for the

(callg fuel) cross-sections with the axial peak power. Therefore, this is the

radially averaged energy deposition versus time in this crosssection

5. Linear power (kW/m), fuel The whole set of these parameters was calculated for the crossenthalpy (callg fuel), energy of the section with the axial peak power according to the energy

metal-water reaction (calg fuel), deposition, obtained in item 4. Calculations of the metal-water

leakage of energy (calg fuel), clad- reaction are not planned by SCANAIR code, and therefore are

to-coolant heat transfer coefficient not presented in the data base. Respective calculations by FRAP-

(kW/m2K) vs. time T6 code are not presented for fuel rods with the air coolant, as

the necessary correlations for the cladding oxidation were

absent.

6. Fuel center line temperature (K), These parameters are calculated for the cross-section with the

fuel surface temperature (K), axial peak power according to the energy deposition, obtained in

fission gas release (%), average item 4. Calculations of ZrO2 thickness were not performed by

ZrO2 thickness (mm) vs. time SCANAIR code for all 13 fuel rods; calculations of ZrO2

thickness by FRAP-T6 code were not performed for the fuel rods

cooled with air because of the reasons mentioned in item 5.

7. Clad outer temperature (K), fuel These parameters were calculated for the cross-section with the

hoop strain (%), fuel-clad gap axial peak power according to the energy deposition, obtained in

width (mm), clad hoop stress item 4

(MPa), internal gas pressure (MPa)

vs. time

8. Fuel swelling (%) This parameter characterizes a change of the fuel volume. It was

calculated for the cross-section with the axial peak power. In

order to determine the hoop component of this parameter, it is

necessary to divide the presented values by 3.

9. Energy deposition at infinite time Axial profile of the energy deposition, obtained according to

vs. axial interval (calg fuel) item 3.

10. Fuel enthalpy vs. axial interval Axial profile of the enthalpy, calculated for the maximum value

(callg fuel) of the energy deposition, obtained according to item 3.

5
2.6. Comments to Appendixes H, I

Appendix H consists of 10 independent appendixes, each of them contains a data base to characterize one of fuel

rods with the irradiated cladding and the fresh fuel during and after IGR tests. Appendix I includes the data base for

two fresh fuel rods. All the commeriti to the data base of Appendix G can also be applied to Appendixes H and I,

but for:

* calculated results of the fuel swelling and the fission gas release were not included into this data base, because

they do not represent any practical interest;

* the notion <undamaged parb> of the fuel column was not used for these fuel rods, therefore the whole fuel

column was considered to be undamaged.

2.7. Comments to Appendix J

The data base to characterize ring tensile tests with unirradiated and irradiated Zr-l%Nb cladding is presented in

this Appendix.

The obtained data base contains the following set of parameters:

* input characteristics of the standard Zr-1 %Nb VVER tube used to fabricate unirradiated ring specimens;

* input characteristics of the commercial VVER fuel clement the cladding of which was used to fabricate irradiated

ring specimens;

* mechanical properties of unirradiated and irradiated Zr-1 %Nb ring specimens versus temperature and strain rate;

* photographs of ring specimens after tests.

Procedures to obtain this data base are described in Chapter 6 of Volume 2.

2.8. Comments to Appendix K

This data base contains results of especially performed burst tests with unirradiated and irradiated Zr-l%Nb

specimens. It consists of input data to characterize both types of specimens before tests and test results. Tests results

are presented by the following parameters:

photographs of specimens after tests and photographs of cross-sections of these specimens;

measured set of burst parameters versus temperature and pressure increase rate.

Description of procedures used to measure testing parameters is presented in Chapter 6 of Volume 2.

6
-APPENDI

Typical Characteristics

-FuelRods before the Irrat

;;- -, 1. .-*;*

,NE6R, f-1.000 ;¢. > 'stz

'n atN;'' VNP.;.'....P"',b;' .ir

A-1
Table A.1. Typical Characteristics of VVER-1000 Fuel Rods before Irradiation at NV NPP

Characteristic Unit Value

1. Fuel U0 2

1.1. Isotopic composition

u23s% by weight 3.58

u238% by weight 96.36

U234 % by weight 0.03

U236 % by weight 0.03

1.2. Total Uranium % by weight 87.88

1.3. Impurity % by weight < 0.08

1.4. Enrichment % 3.58

1.5. Oxygen coefficient per-unit 2.000 - 2.015

1.6. Density g/cm 3 10.6 ± 0.2

1.7. Grain size gm 4 -8

1.8. Pellet shape . cylinder with central hole

1.9. Pellet outer diameter mm 7.5 002i.

1.10. Pellet inner diameter mm 2A4- 5

1.11. Pellet height mm :21 5

2. Cladding (Zr-i %Nb)

2.1. Composition:

Zr % by weight 98.67 - 98.87

Nb %byweight 0.9- 1.1

0 % by weight < 0.1

N, C, Si, Al, Mo, Ni, Fe % by weight < 0.13

2.2. Cold work cold rolling, annealing, autoclaving

2.3. Outer diameter mm 9.05

2.4. Inner diameter mm 7.72+o8.0

2.5. Material properties(under standard conditions):

* Specific heat capacity kJ/kg-°C 0.25

* Thermal conductivity W/m-°C 17.2

* Linear expansion coefficient W/C 5.8.104

* Density gfcm3 6.55

* Young's modulus MPa 9.4.104

. P0.346 (axial) * Poisson's ratio 0.354 (radial)

380-440 (axial) * Ultimate tensile strength MPa 360420 (radial)

210-260 (axial) * Conventional yield limit a MPa 320-390 (radial)

A-2
Table A.1. Typical Characteristics of VVER-I000 Fuel Rods before Irradiation at NV NPP (contd)

Characteristic Unit Value

3. Fuel rod

3.1 Fuel rod design see Fig. A.1

3.2 Upper plenum volume cm3 9.69

3.3 Lower plenum volume cm3 0.24

3.4 Pellet stack length mm 3530 412

3.5 Fuel rod length mm 3837+22

3.6 Initial fill pressure MPa 2.0 - 2.5

3.7 Fill-gas composition:

He % by volume > 99.99

Impurity % by volume < 0.01

3.8 Fixing rings (SS-08Xl8H I OT):

number 3

outer diameter mm 8.2

inner diameter mm 7.2

height mm 8.9 -0.9

4. Fuel assembly

4.1 Fuel rods number . 317

4.2 Grid type Hexagonal

4.3 Spacer grid pitch mm 12.75

4.4 Spacer grid material SS

4.5 Spacer grid number 15

A-3
Fig. A.I. Design Scheme of NV NPP Commercial Fuel Rod

A-4
B-1
Position 2

101.0N

Position I

Fig. B.1. Cross-Section Appearance, Cladding and Fuel Microstructure for the Fuel Rod #317

B-2
Table B.1. NV NPP Operating Cycles Characteristics

Characteristic Unit Value

1. Number of cycles 3

2. Operation periods eff.day 298.1; 321.6; 301.4

3. Irradiation beginning June 25, 1984

4. Irradiation end June 25, 1987

5. Power history see Fig. B.2

6. Inlet coolant temperatures during the basic operating mode:

1"S cycle 0C 287.3 - 288.7

2nd cycle 0C 287.7 - 288.3

3Yd cycle 0C 287.1 - 288.0

7. Outlet coolant temperatures:

1S cycle 0C 316.9 - 319

2nd cycle 0C 323 - 326.0

3r cycle 0C 317.3 - 318.9

8. Inlet coolant pressure (1 ", 2d, 3dcycles) MPa 15.7

9. Pressure drop in the core MPa 0.33 - 0.35

B-3
Table B.2. Characteristics of Commercial Fuel Rods after Irradiation at NV NPP

Characteristic I Unit I Value

1. Fuel

1.1. Isotopic composition (for fuel rod #317, elevation 1800 mm from the bottom of the fuel stack):

U235

10236

u 23 8

Pu23 9

p6239*

Pu2 40

Pu2 4 1

Pu2 4 2

Am2 4 3

1.2. Burnup:

for fuel rod #307 (elevation - 1800 mm from the

bottom of the fuel stack)

for fuel rod #317 (elevation - 1850 mm from the

bottom of the fuel stack)

1.3. Density for fuel rod #307 at different elevations

(coordinates from the upper end of the fuel rod):

242 mm

1042 mm

1872 mm

2642 mm

3452 mm

1.4. Average pellet outer diameter (fuel rods #22,

#307)

1.5. Diameter of central hole:

for fuel rod #317

for fuel rod #22

kg/t U

kglt U

kg/t U

kg/t U

kg/t U

kg/t U

kg/t U

kg/t U

kg/t U -

kg/t U

GWd/t U

kg/lt U

GWd/t U

g/cm3

g/cm3

g/cm3

g/cm3

g/cm3

mm

4.35

4.92

927.5

0.31

5.00

2.62

1.64

1.12

0.287

52.4*, 52**

50.6*, 50.3**

53.9*, 52**

52.1*, 50.3**

10.41

10.31

10.32

10.31

10.48

7.55 - 7.60

mm

mm

2.40

2.415

2. Cladding

2.1. Cladding thickness:

for fuel rod #317 .1m 691 - 705

for fuel rod #22 Pm 677 - 700

2.2. ZrO2 thickness . Pm 3 - 5

2.3. Coefficient of the hydride orientation:

for fuel rod #317 per-unit 0.4

for fuel rod #22 per-unit 0.14

B4
Table B.2. Characteristics of Commercial Fuel Rods after Irradiation at NV NPP (contd.)

Characteristic Unit Value

3. Fuel rods

3.1. Fuel stack length:

fuel rod #22 mm 3562

fuel rod #307 mm 3585

3.2. Width of the gap between the fuel and cladding mm 0.03 - 0.15***

along fuel rods #22, #307

3.3. Average gas pressure inside fuel rods MPa 2.45

3.4. Average gas volume inside fuel rods cm3 35.9

3.5. Average gas composition inside fuel rods:

He % by volume 94.2 - 98.9

Kr % by volume 0.11 -0.60

Xe % by volume 0.84 - 5.04

N 2 % by volume 0.06 - 0.23

02 % by volume 0.01 - 0.06

Ar % by volume 0.002 - 0.005

CO2 % by volume 0.002 - 0.003

3.6. Axial burnup distribution for fuel rods #317, see Table B.3, Fig. B.3

#22

3.7. Radial bumup distribution for fuel rod #317

(coordinate from inner side of pellet), mm:

0.61 MWd/kg 46.5

1.41 MWd/kg 46.9

1.9 MWd/kg 47.3

2.12 MWd/kg 50.1

2.17 MWd/kg . 54.3

3.8. Radial distribution of isotopes for fuel rod

# 317 see Table B.4

' accumulation of fission products measured by the mass-spectrometrical method

*' changes in isotopic ratios of heavy nuclei measured by the mass-spectrometrical method

" ' smaller value is for the central part of fuel rods

B-5
Table B3. Axial Distribution of Burnup for Fuel Rods #22, #317 after Irradiation at NV NPP

Fuel rod #22 Fuel rod #317

Coordinate from the Bunup Coordinate from the Burup

lower end of the rod I(MW ) lower end of the rod J (MWd )

(mm) (mm) ,

3810.1 0.009 3810.93 0.009

3800.1 -0.009 3800.93 0.000

3700.1 -0.006 3700.93 0.017

3600.1 -0.018 3600.93 -0.001

3500.1 20.645 . 3500.93 25.536

3400.1 29.018 3400.93 34.678

3300.1 33.853 3300.93 39.271

3200.1 37.340 3200.93 43.820

3100.1 39.619 3100.93 44.787

3000.1 41.712 3000.93 47.255

2900.1 43.221 2900.93 47.072

2800.1 42.459 2800.93 47.406

2700.1 43.056 2700.93 50.270

2600.1 43.354 2600.93 48.952

2500.1 43.315 2500.93 48.946

2400.1 43.662 2400.93 49.045

2300.1 42.279 2300.93 48.092

2200.1 43.470 2200.93 49.241

2100.1 43.360 2100.93 49.135

2000.1 43.995 2000.93 48.750

1900.1 44.118 1900.93 50.076

1800.1 42.034 1800.93 47.807

1700.1 43.566 1700.93 50.745

1600.1 43.866 1600.93 50.181

1500.1 44.072 1500.93 50.192

1400.1 43.849 1400.93 50.054

1300.1 41.803 1300.93 47.582

1200.1 43.313 1200.93 50.346

1100.1 43.653 1100.93 50.181

1000.1 43.149 1000.93 49.488

900.1 43.907 900.93 50.562

800.1 42.623 800.93 49.871

700.1 43.659 700.93 50.537

600.1 42.944 601.72 49.478

500.1 41.498 501.72 47.596

400.1 41.184 401.72 47.180

300.1 37.603 301.72 43.703

220.1 34.747 221.72 40.407

B-6
Table B.4. Measured Radial Distribution of Isotopic Composition (kg/t U) for Fuel Rod #317

Coordinate from the inner side of the pellet (mm)

0.61 1.41 1.90 2.12 2.17

u2340.19 0.19 0.19 0.27 0.28

u235 6.12 5.89 5.63 5.43 5.20

u236 4.99 5.08 5.16 5.25 5.30

u23r 929.35 928.90 928.07 924.51 918.65

Pu23 0.30 0.31 0.31 0.31 0.30

PU239 5.38 5.41 5.50 5.91 6.61

Pu240 2.60 2.62 2.64 2.65 2.67

pu24

1 1.68 1.69 1.86 2.01 2.35

Pu242 0.89 0.90 1.00 1.11 1.37

3500

i

O

>1

a

19

E

tl_--

3000

2500

2000

1500

1000

500

0

Time (eff. day)

Fig. B.2. Power History for Unit 5 of NV NPP

B-7
60 1 .L L _IL... .

40 -- _ %I-_ _Wv V 

200-l;

0 800 1600 2400 3200 4000

a) Fucl rod lcngth (mm)

60-

40 -

20 -

0 I l l

0 800 1600 2400 3200 4000

b) Fuel rod length (mm)

Fig. B.3. Axial Burnup Distribution for Fuel Rod #22 (a), #317 (b)

B-8
C-1
Table C.1. Initial Characteristics of Refabricated Fuel Rods before IGR Reactor Tests.

Representative values

Characteristic Unit Value

1. Fuel

1.1. Pellet outer diameter mm 7.55 - 7.60

1.2. Pellet inner diameter mm 2.4

1.3. Pellet height mm 9 - 14

1.4. Density g/cm3 10.31 - 10.32

1.5. Grain size Pm 3.9

1.6. Fuel shape Fuel pellets, fragments of

1.7. Fuel macrostructure see Fig. C.1

1.8. Fuel microstructure see Fig. C.1

2. Cladding

2.1. Cladding outer diameter mm 9.1 02

2.2. Cladding inner diameter mm not measured

2.3. Corrosion thickness gim 5- 6

2.4. H2 content in cladding % by weight 3 - 6 10-3

2.5. Cladding microstructure see Fig. C.1

3. Fuel rod

3.1. Fuel rod design see Fig. C.2

3.2. Fuel rod length mm 300

3.3. Initial fill pressure MPa 1.7+0 2

3.4. Gas composition:

He % by volume 97.57

Impurity % by volume 2.43

3.5. Free volume cm3 6.11 (average)

C-2
Fig. C.1. Typical Cross-Section Appearance, Cladding and Fuel Microstructure of Refabricated Fuel

Rod before IGR Reactor Test

C-3
1. Lower cap

2. Fixing ring

3. Fuel pellet

4. Connector

5. Upper plenum

6. Upper cap

L,, I,,, I, L4-individual values

for each fuel rod

(see Tables C.2.1 - C.2.3)

Fig. C.2. Design Scheme of Refabricated Fuel Rod

C4
Initial Ind aracteristics of Refabricated Fuel Rods -|

, (Preiriadia :ielrirradiated cladding),. ' : . . I .-..

Table C.2.1. Consolidated List of Characteristics for Fuel Rods ##HIT, H2T, H3T, H4T, H5T

Number of fuel rod

Characteristic

HIT H2T H3T H4T H5T

I .Identification number of

commercial fuel rods used for 317 317 317 317 317

refabrication

2.Coordinates of commercial 1500 2740 930 1980 2550

fuel rod sections used for refab- 1650 2890 1080 2130 2700

rication (see Fig.A.I) (mm)*

3.Coordinates of fuel stack for 21.5 19.5 19.5 11.5 23.0

refabricated fuel rods (mm)')* 178.0 169.5 174.5 166.5 179.0

4.Coordinates of undamaged 47.5 19.5 32.5 27.5 42.5 87.5

sections of fuel stack for refab- 178.0 169.5 157.5 166.5 72.5 157.5

ricated fuel rods (mm)*

5.Length of undamaged sections 130.5 150.0 125.0 139.0 30.0 70.0

of fuel stack (mm).

6.Average burnup of refabri- 49.2 47.9 49.3 48.7 49.0

cated fuel rods (MWd/kg U) __

7.Total fuel mass (g) 60.4 61.2 60.6 59.8 57.0

8.Fucl mass for undamaged 53.5 61.2 51.1 56.7 39.5

sections (g) 53_5 61_2 ____ 56_7_39_5

9.L, (see Fig. C.2) (mm) 0.0 0.1 0.1 0. 0.2

1O.L2 (see Fig. C.2) (mm) 2.1 0.0 0.0 0. 3.4

1 I.L, (see Fig. C.2) (mm) 156.5 150.0 155.0 147.12) 156.0

12.L4 (see Fig. C.2) (mm) 1.5 10.0 5.0 13.0 0.5

13.Total gas volume (cm3) 5.76 5.68 5.74 5.82 6.09

14.Average outer diameter of 9.11 9.09 9.11 9.11 9.08

cladding (mm) I

15.Fuel-cladding radial gap 0.03 0.03 0.03 0.03 0.03

(m m ) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

' From lower end of fuel rod

I)Taken into account y-scanning results

2) Length of the fuel stack ignoring fuel fragments inside fixing ring -

C-5
' Initial Individual C eristics of Refabricated Fuel Rods .:.

(Preirradiated f15e661,7r iated cladding) - ; ITablc C.2.2. Consolidated List of Characteristics for Fuel Rods ##H6T, H7T, H8T, B9T

Number of fuel rod

Characteristic

H6T H7T H8T B9T

1.Identification number of

commercial fuel rods used for 317 317 317 317

refabrication

2.Coordinates of commercial 550 360 2930 1120

fuel rod sections used for refab- 700 510 3080 1270

rication (see Fig.A.1) (mm)*

3.Coordinates of fuel stack for 13.0 21.5 10.5 20.0

refabricated fuel rods (mm)')* 178.0 179.5 177.5 170.0

4.Coordinates of undamaged 32.5 102.5 47.5 107.5 102.5 20.0

sections of fuel stack for refab- 42.5 132.5 97.5 167.5 177.5 157.5

ricated fuel rods (mm)*

5.Length of undamaged sections 10.0 30.0 50.0 60.0 75.0 137.5

of fuel stack (mm)

6.Average burnup of refabri- 49.3 47.3 46.8 49.7

cated fuel rods (MWd/kg U)

7.Total fuel mass (g) 49.2 56.8 56.2 58.9

8. Fuel mass for undamaged 16.6 42.6 30.7 56.1

sections (g) 16__4_6_0 _ 56_1

9.L, (see Fig. C.2) (mm) 0. 0.0 0. 0.3

1 O.L2 (see Fig. C.2) (mm) 0. 2.1 0. 0.3

I I.L, (see Fig. C.2) (mm) 158.62) 158.0 158.12) 150.0

12.L, (see Fig. C.2) (mm) 1.5 0.0 2.0 9.5

13.Total gas volume (cm3) 6.96 6.11 6.17 5.91

14.Average outer diameter of 9.11 9.11 9.11 9.08

cladding (mm)

15.Fuel-cladding radial gap 0.03 0.07 0.03 0.03

(m m ) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

From lower end of fuel rod

) Taken into account y-scanning results

2) Length of the fuel stack ignoring fuel fragments inside fixing ring

C-6
Initial IndiviITaCharacteristics of Refabricated Fuel Rods i:

(Preirradiat, lPrirradiated cladding), - ' -, - I I -

Table C.2.3. Consolidated List of Characteristics for Fuel Rods ##BIOT, B11T, B12T, B13T

Number of fuel rod

Characteristic

BIOT BIT B12T B13T

1.dentification number of

commercial fuel rods used for 22 22 317 22

refabrication

2.Coordinates of commercial 2530 2340 2170 350

fuel rod sections used for refab- 2680 2490 2320 500

rication (see Fig.A.1) (mm)*

3.Coordinates of fuel stack for 25.0 18.5 10.5 19.5

refabricated fuel rods (mm)')* 173.0 178.5 172.5 175.5

4.Coordinates of undamaged 37.5 27.5 112.5 19.5

sections of fuel stack for refab- 142.5 122.5 137.5 157.5

ricated fuel rods (mm)*

5.Length of undamaged sections 105.0 95.0 25.0 139.0

of fuel stack (mm)

6.Average burnup of refabri- 43.0 43.6 48.7 41.0

cated fuel rods (MWd/kg U) 43.0_43_6_48 .7_410

7.Total fuel mass(g) 55.5 57.4 47.9 59.3

8. Fuel mass for undamaged 43.5 38.5 10.2 56.2

sections(g)

9.L, (see Fig. C.2) (mm) 4.6 0. 0. 0.1

I O.L2 (see Fig. C.2) (mm) 1.0 0. 0. 0.0

I 1.L,3 (see Fig. C.2) (mm) 148.0 159.12) 153.12) 156.0

12.L, (see Fig. C.2) (mm) 6.5 1.0 7.0 4.0

13.Total gas volume (cm3

) 6.20 6.02 6.99 5.97

14.Average outer diameter of 9.08 9.10 9.09 9.09

cladding (mm)

15.Fuel-cladding radial gap 0.07 0.07 0.03 0.07

(mm)

From lower end of fuel rod

I) Taken into account y-scanning results

2) Length of the fuel stack ignoring fuel fragments inside fixing ring

C-7
Initial Individual Cdlci teristics of Refabricated Fuel Rods -

(Preif idiated fue1zPildiated cladding)

Table C.3. Free Gas Volume in Refabricated Fuel Rods before IGR Reactor Tests at Axial Coordinates 185+295 mm

Axial coordinate Free gas volume

(from lower end (mm3)

of fuclrod)

(mm) HIT |H2T |H3T H4T H5T H6T H7T H8T B9T BIOT BIIT BI2T BI3T

185 53 53 53 53 53 53 53 53 53 53 53 53 53

195 71 71 71 71 71 71 71 71 71 71 71 71 71

205 250 250 250 250 250 250 250 250 250 250 250 250 250

215 468 468 468 468 468 468 468 468 468 468 468 468 468

225 468 468 468 468 468 468 468 468 468 468 468 468 468

235 468 468 468 468 468 468 468 468 468 468 468 468 468

245 468 468 468 468 468 468 468 468 468 468 468 468 468

255 468 468 468 468 468 468 468 468 468 468 468 468 468

265 468 468 468 468 468 468 468 468 468 468 468 468 468

275 468 468 468 468 468 468 468 468 468 468 468 468 468

285 119 119 ) 119 11 119 119 119 119 119 119 1l9 119 1

295 0 0 0 0 0 0 0 0 0 0 0 0 0

C-8
C-9
#H1T | lninlaIn~nJ~i ote~f RefabricatedFiiei Rods7- -> |

[ (g claddinig) - I -V In

Table C-1.1. Axial Distribution of Isotopic Composition for Fuel Rod #H1T (calculated)

Axial coordinate Nuclear concentrations

from lower end (kg/t U)

of fuel rod

(mm) U235 I UB6 I U238 I pu239 I pu240 I PU241 I pU242

20

25

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

165

170

175

180

4.76

4.76

4.76

4.76

4.76

4.71

5.14

5.11

5.06

5.03

5.00

5.17

5.28

5.19

5.08

5.08

5.08

5.00

4.92

4.84

4.81

4.68

4.60

4.53

4.45

4.60

4.73

4.71

4.68

4.79

4.89

4.71

4.58

4.94

4.94

4.94

4.94

4.94

4.94

4.90

4.91

4.91

4.91

4.92

4.90

4.89

.4.90

4.91

4.91

4.91

4.92

4.92

4.93

4.93

4.94

4.95

4.96

4.96

4.95

4.94

4.94

4.94

4.93

4.93

4.94

4.95

927

927

927

927

927

927

928

928

928

928

928

928

929

928

928

928

928

928

927

927

927

927

926

926

926

926

927

927

927

927

927

927

926

4.99

4.99

4.99

4.99

4.99

4.98

5.05

5.05

5.04

5.03

5.03

5.06

5.08

5.06

5.04

5.04

5.04

5.03

5.02

5.01

5.00

4.98

4.96

4.94

4.92

4.96

4.99

4.98

4.98

5.00

5.01

4.98

4.95

2.66

2.66

2.66

2.66

2.66

2.66

2.61

2.62

2.63

2.63

2.63

2.61

2.60

2.61

2.62

2.62

2.62

2.63

2.64

2.65

2.65

2.67

2.68

2.69

2.70

2.68

2.66

2.66

2.67

2.65

2.64

2.66

2.68

1.616

1.616

1.616

1.616

1.616

1.616

1.606

1.606

1.607

1.607

1.608

1.605

1.603

1.605

1.606

1.606

1.606

1.608

1.611

1.615

1.615

1.616

1.616

1.617

1.617

1.616

1.616

1.616

1.616

1.615

1.612

1.616

1.616

1.049

1.049

1.049

1.049

1.049

1.058

0.990

0.994

1.003

1.007

1.011

0.986

0.969

0.982

0.998

0.998

0.998

1.011

1.024

1.036

1.041

1.062

1.075

1.088

1.101

1.075

1.054

1.058

1.062

1.045

1.028

1.058

1.079

All numerical values ofcharacteristics are presented as average values at the length interval equal to the axial coordinate ± 2.5 mm

C-10
#H1T I dofaRef bncatedFueiiRods hi

0IjiP eiira-d ua diat d., -,adding);--

Table C-1.2. Radial Distribution of Burnup (Calculated) and Isotopic Composition with RIM Zone

Indication (Calculated) for Fuel Rod #HIT (average values in fuel rod)

Coordinates of fuel radial zones (mm)

Characteristic I zone 2 zone 3 zone 4 zone

1.2 - 2.811 2.811 - 3.432 3.432 - 3.704 3.704 - 3.790

I. Nuclear concentrations

(kg/t U):

u235 4.98 4.78 4.59 4.46

U236 4.93 4.93 4.93 4.94

0238 933. 930. 917. 884.

Pue9 4.20 4.68 6.29 10.66

Pu240 2.35 2.46 3.14 5.08

pu24' 1.293 1.503 2.118 3.777

Pu242 0.809 0.966 1.401 2.581

2. Burnup 44.9 47.8 56.1 78.7

(MWd/kg U)

C-i I
#H1,T Table IddfuclntiaCaacteistics H--'T'(measured)forFuelRodt' Fuel Rod -

Table C-13. Individual Initial Characteristics for Fuel Rod #HIT (measured)

Axial coordi- Cladding Cladding Fuel mass (g) Linear Free gas Burnup

nate from outer outer (density- fuel volume (MWd/kg U)*

lower end diameter diameter 10.134) g/cm3)* mass (mm,)")

of fuel rod at 00 at 900 (g/cm)*

(mm) (mm) (mm)

5 0.00 0.00 8.8

10 - - 0.00 0.00 98.9 0.0

15 - - 0.00 0.00 234.0 0.0

20') - - 0.38 3.80 196.6 49.63)

25 - - 1.61 3.22 75.6 49.63)

30 - - 0.90 1.80 145.5 49.63)

35 - - 1.22 2.43 114.0 49.63)

40 - - 1.16 2.32 119.9 49.63)

45 9.114 9.111 1.88 3.76 49.0 49.63)

50 9.105 9.111 1.99 3.98 38.2 48.1

55 9.117 9.113 1.99 3.99 38.2 48.3

60 9.125 9.099 2.01 4.01 36.2 48.4

65 9.126 9.101 2.01 4.03 36.2 48.5

70 9.119 9.108 2.05 4.09 32.3 48.6

75 9.114 9.111 2.06 4.12 31.3 48.1

80 9.120 9.117 2.07 4.13 30.3 47.6

85 9.123 9.117 2.08 4.16 29.3 48.0

90 9.117 9.126 2.09 4.18 28.3 48.3

95 9.114 9.125 2.07 4.15 30.3 48.3

100 9.113 9.116 2.04 4.08 33.3 48.3

105 9.116 9.116 2.04 4.08 33.3 48.7

110 9.113 9.116 2.04 4.08 33.3 49.0

115 9.108 9.116 2.04 4.07 33.3 49.2

120 9.110 9.110 2.04 4.07 33.3 49.4

125 9.113 9.107 2.06 4.12 31.3 49.8

130 9.117 9.108 2.04 4.08 33.3 50.2

135 9.122 9.113 2.03 4.06 34.2 50.5

140 9.111 9.116 2.03 4.07 34.2 50.8

145 9.108 9.122 2.04 4.09 33.3 50.1

150 9.116 9.110 2.04 4.09 33.3 49.6

155 9.117 9.099 2.06 4.12 31.3 49.8

160 9.123 9.102 2.06 4.12 31.3 49.9

165 9.114 9.111 2.04 4.08 33.3 49.4

170 9.116 9.113 2.04 4.07 33.3 49.1

175 9.114 9.114 1.98 3.95 39.2 49.8

1802) 9.110 9.135 0.21 4.20 91.4 50.3

. These numerical values ofcharacteristics are presented as average values at the length interval equal to the axial coordinate ± 2.5 mm

I) Initial coordinate of fuel is 11.5 mm 4) Effective density of fuel stack

2) Final coordinate of fuel is 166.5 mm 5) Free gas volume for coordinates lS5 - 295 mm

3) Average value is presented in Table C.3

C-12
#H1T t|;ita~ia. cteriiics f Refabricated Fuel Rotils ' ,'

iatid cladding) - ',,N '- I

(12

(12

4)

0 50 100 150 200

a) Axial coordinate (mm)

250

_ _

b)

5.0

4.0

U,

En

.z

3.0

2.0

E

C'S

0

1.0

0

0 50 100 150 200 250

c) Axial coordinate (mm)

Fig. C-1.1. (a) Results of y-scanning, (b) Radiography, (c) Axial Fuel Mass Distribution and Axial Free

Gas Volume Distribution for Fuel Rod #H1T

C-13
#H1T ' °IfRddbicfnt)' Fl Rods",

I - I

nE

mo

50 -' ; - -1

40 -

30-

05.0 100 150 26002 50

a) Axial coordinate (mm)

9.4

IE

E .. 9.3

0

,, 9.2 IU

0

= 9.1

9.0

b) Axial coordinate (mm)

1.0

0 0.5

0.0

0

0

*0

I= .0.5

E -

-1.0

_ I mode

2 mode...................- 

............. ,.............................. ... ....._ ':..,.............

0 50 100 150 200 250

c) Axial coordinate (mm)

Fig. C-1.2. (a) Axial Burnup Distribution and (b) Results of Profilometry and (c) Eddy-Current

Examination for Fuel Rod #H1T

Ir- C-14
IIHn IT Iz T I.b .'U- -II. ', 

10

En I

E

cf

0

U

(z

8

6

4

, .,_ A....,..'b'pU'21 ' .............. _.

U2 3 8 3

pu 241

0 40 80 120 160

a) Axial coordinate (mm)

1000

800

600

400

~1~

200

0

2

0

1.2

4-.

0

0

U

le

0

a

r_

-

no

0s

UN5

1.0

0.8 -

0.6 -

A

II

I.

III

A

0.4 -1

0.2 -+- , . .- .5. -. 5

3

I

. 1 2 4

b) Radial fuel coordinate (mm)

Fig. C-1.3. (a) Axial Distribution of U135, Un3s, Pu23 9, Pu241 Isotopes and (b) Radial Distribution

of U235 Isotope for Fuel Rod #HIT (calculated)

C-15
#HIT Cof Refabricated Fuel Rods1⁄2e Ik-.. I i add ;dlrkd il',, li. I

.E0

C

0

L.. *_ c

U:-

_ L

7 C

Ve

1.2

1.0

0.8

0.6

0.4

0.2 I.

1 2 . .3

Radial fuel coordinate (mm)

4

2

Eo

2

4..P

O

a

rc) L

Z s

1.2

1.0

0.8

0.6

0.4

0.2

Radial fuel coordinate (mm)

Fig. C-1.4. Radial Distribution of Pu239, Pu241 Isotopes for Fuel Rod #HIT (calculated)

C-16
#H1T Inta nMd Cara ~dc; fea~iai ~~RdI

~irrarn~u ~iimiat~d ~iddizi:Q ;fg~

C.)

0

.0

9.

a

.6.

C3s

1.2 -

1.0 -

U M

... . ..... ...... _

-, _

=

0.8-.

0.6-4 I

I

I

II,

. '1} J ,..

....- d .,

^,, !, b

> *>4.t .

' t ' i., '

".;,: ', ,". '

'.; . .:

1 Q

,;_,,,

r m- < . . a .

. ,,; . p .S

. s.i ...- . .....

,.,' t .:

., '.' . as

: ...-.? h

I . ,s'', .

.w

'.'.F ,, ., '

;s','.. ;:, '. -,.< .. ._...

., - .,., z t

Ill

L

A

0.4 -

0.2 - _ _ , . ~. . _ _

I

I 2 3

I 4

a) Radial fuel coordinate (mm)

1.2

*20.Fz

cd

4-.

C)

3a

E

iT_ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ I__ _ _ _ _ _

'n

0.8 -

0.6 -

0.4 -

$ 4

I - I

_

1

2

II

HI.

'V

0.2 - - . -

3

I

b) Radial fuel coordinate (mm)

Fig. C-1.5. (a) Radial Distribution of U23 Isotope and (b) Burnup for Fuel Rod #H1T (calculated)

C-17

C-19
#H2T I n"iiiafin¶ef' ab ncatiso e~ i~i~ d Fue'lRo d5~ x'i

| an- RM" rsd -,d='6 cIaduf ,.,!+_;,o ,-

Table C-2.1. Axial Distribution of Isotopic Composition for Fuel Rod #H2T (calculated)

Axial coordinate Nuclear concentrations

from lower end (kg/t U)

of fuel rod

(mm) I u235 I U236 I U238 I Pu239 I pu24 0 I pu241 I pu 242

20

25

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

165

170

175

180

5.33

5.33

5.27

5.25

5.25

5.25

5.06

4.93

i 5.09

5.19

5.22

525

5.47

5.63

5.75

5.83

5.86

5.89

5.95

5.98

5.98

6.01

5.72

5.55

5.58

5.58

5.55

5.55

5.27

*5.09

5.09

4.91

4.91

4.91

4.91

4.91

4.91

4.93

4.94

4.93

4.92

4.92

4.91

4.89

4.88

4.87

4.86

4.86

4.85

4.85

4.85

4.85

4.84

4.87

4.89

4.88

4.88

4.89

4.89

4.91

4.93

4.93

927

927

927

927

927

927

926

926

926

927

927

927

927

928

928

929

929

929

929

929

929

929

928

928

928

928

928

928

927

926

926

5.30

5.30

5.29

5.29

5.29

5.29

5.26

523

5.27

5.28

5.28

5.29

5.32

5.35

5.37

5.38

5.38

5.39

5.39

5.40

5.40

5.40

5.36

5.34

5.34

5.34

5.34

5.34

5.29

5.27

5.27

2.68

2.68

*2.69

2.69.

2.69

2.69

2.71

2.73

2.71

2.69

2.69

2.69

2.66

2.64

2.62

2.61

2.61

2.61

2.60

2.60

2.60

2.59

2.63

2.65

2.65

2.65

2.65

2.65

2.69

2.71

2.71

1.691

1.691

1.692

1.693

1.693

1.693

1.700

1.702

1.700

1.696

1.695

1.693

1.687

1.683

1.679

1.675

1.674

1.672

1.670

1.669

1.669

1.667

1.680

1.685

1.684

1.684

1.685

1.685

1.692

1.700

1.700

1.003

1.003

1.012

1.016

1.016

1.016

1.045

1.066

1.041

1.024

1.020

1.016

0.983

0.958

0.942

0.930

0.926

0.922

0.914

0.910

0.910

0.906

0.946

0.970

0.966

0.966

0.970

0.970

1.012

1.041

1.041

All numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate * 2.5 mm

C-20
#H2T d1n~fl'ii~ii)Ctetics of Rceabricated FtuelRodi.i, :|

| ..t zaIn 11,nAMRadiated cladding) ,

Table C-2.2. Radial Distribution of Burnup (Calculated) and Isotopic Composition with RIM Zone

Indication (Calculated) for Fuel Rod #H2T (average values In fuel rod)

Coordinates of fuel radial zones (mm)

Characteristic I zone 2 zone 3 zone 4 zone

1.2 - 2.811 2.811 - 3.432 3.432 - 3.704 3.704 - 3.790

1. Nuclear concentrations

(kg/t U):

5.63 5.41 5.21 5.07

U236 4.89 4.90 4.90 4.90

U238 934. 930. 918. 885.

PU239 4.46 4.97 6.70 11.39

Pu240 2.35 2.47. 3.16 5.13

Pu241 1.348 1.571 2.221 3.974

Pu242 0.766 0.916 1.330 2.453

2. Burnup 43.8 46.6 54.8 76.7

(MWd/kg U)

C-21
#H2T 1 cea a R1eitiAi.J icaft ,eed, iu "'' ''

.1; t df if ad at d laddir g)' I I

Table C-23. Individual Initial Characteristics for Fuel Rod #1H2T (measured)

Axial coordi- Cladding Cladding Fuel mass (g) Linear Free gas Burnup

nate from outer outer (density- fuel volume (MWd/kg U)*

lower end diameter diameter 10.134) g/cml)* mass (mm3)*5)

of fuel rod at 00 at 900 (g/cm)*

(mm) (mm) (mm) __ _

5

10

15

20')

25

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

165

1702)

175

180

9.097

9.100

9.104

9.098

9.094

9.088

9.086

9.097

9.094

9.084

9.084

9.091

9.095

9.089

9.077

9.078

9.086

9.098

9.103

9.098

9.098

9.098

9.094

9.092

9.091

9.098

9.107

9.107

9.112

9.101

9.095

9.089

9.094

9.091

9.084

9.078

9.083

9.098

9.097

9.089

9.084

9.088

9.097

9.101

9.097

9.097

9.098

9.107

9.100

9.095

9.094

9.098

9.106

9.091

9.092

9.092

0.0

0.0

0.0

1.20

2.04

2.05

2.06

2.05

2.01

2.01

2.00

1.98

1.99

2.04

2.06

2.07

2.09

2.09

2.06

2.03

2.00

2.01

2.01

2.02

2.03

2.05

2.07

2.08

2.10

2.10

2.09

2.03

2.00

0.79

0.0

0.0

0.0

0.0

0.0

4.01

4.09

4.10

4.13

4.10

4.03

4.02

4.01

3.96

3.99

4.08

4.12

4.14

4.17

4.18

4.12

4.05

4.01

4.01

4.02

4.04

4.06

4.09

4.13

4.17

4.20

4.21

4.17

4.06

4.01

3.94

0.0

0.0

8.8

98.9

234.0

115.9

33.3

32.3

31.3

32.3

36.2

36.2

37.2

39.2

38.2

33.3

31.3

30.3

28.3

28.3

31.3

34.2

37.2

36.2

36.2

35.2

34.2

32.3

30.3

29.3

27.3

27.3

28.3

34.2

37.2

166.3

234.0

114.8

0.0

0.0

0.0

48.63)

48.63)

48.8

48.9

48.8

48.8

49.6

50.0

49.4

49.0

48.9

48.9

48.0

47A

47.0

46.7

46.6

46.5

46.3

46.2

46.2

46.1

47.1

47.7

47.7

47.6

47.7

47.8

48.8

49.5

49.5

0.0

0.0

0 These numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate ± 2.5 mm

1) Initial coordinate offuel is 11.5 mm 4) Effective density offuel stack

2) Final coordinate oftuel is 166.5 mm

3) Average value

5

)Free gas volume for coordinates 15 - 295 mm

is presented in Table C3

C-22
#H2T I~~A~it~~~ciedstC--S-OfIlfbctd ulR

KP~taA-Ii-adiied laddhigY

s ZAAA

1711ftnI . . WVVV

I Cs1371

10000- I Ru106

E0.

8000-

6000-

4000-

2000-

u- -- I I I I I I - I I

0 50 100 150 200 250

a) Axial coordinate (mm)

b)

I .' . 5. innf 'v

L~22LJ

4.0 -

1

9

-E'b

2

E

0

e

.5

.j

3.0 -

2.0 -

A nn

-80

-60 i

-40 0

- Cs

1.0 - -20

U I I I I I I I I I

0 50 100 150 200

c) Axial coordinatc (mm)

0

250

Fig. C-2.1. (a) Results of y-scanning, (b) Radiography, (c) Axial Fuel Mass Distribution and Axial Free

Gas Volume Distribution for Fuel Rod #H2T

C-23
#H2T I 'i&' na idl ncs'ofRefabntd Fuel Rids1 (Pt

~j f>5i~amd claddi r,, ,j |

60 -

40

30 i II

ID 50 100 150 200 0

Axial coordinate (mm)

25

a)

9.4

E

I.-

0'

lI0

to

*r

la

t9

U

lz

.a

C9.3

9.2

9.1

9.0

b) Axial coordinate (mm)

250

c) Axial coordinate (mm)

Fig. C-2.2. (a) Axial Burnup Distribution and (b) Results of Profilometry and (c) Eddy-Current

Examination for Fuel Rod #fH2T

C-24
#H2T ~jU1 Ch ulRd iusisfeznae I 11maia O edM Prrad~idtd~idding). I .'

10

ab

z3

Pi1

F

18

Cn

C>

.9

8

6

4

2

U23

U235

_ ~~~~~~~.. .. ........... .. .... ' '''U4 ............_

Pu239

Pu241

0 40 80 120 160

a) Axial coordinate (mm)

1000

800 L

C"-

0

600 C

400 0

U

200

0 0

1.2

C)

0

0

C)

0

O

.20Z01 ~

U 5

1.0 -I-r..... ....

0.8 -

0.6-I

.<- . 9 < - > . - r v ( - . -, X r: . ' * . . t S ox . . < z Z

-, ,,@;t . f; ,sit,; . _, ''.,:,. o'-',' ,.- t * 2 . A; ,

. 7 f s o;.es; t+ - ;.s, A. st''sa-> ';' [,

s 'st @ >s > E z - - v <- , .$ J -,  B l s e, - t ,

LL r* .; A ' ' 9 , ,..-,-xt.<,,,.,--\.r-' '

,, . i-,. ;

Eese';i''.il';'..'$X

I i - , ., it e, Fs r.. + s

| i . 1 Wl f : . ii .--- . i :. v :j

i i i-s: f sw st* s s f ! j

lgi !. . , v , - i  !'< -u s' f4 t' t.9 8

l

11

,JI:

IV

L

0.4 -

0.2 - ... . , , .... , .. , _-

I I

I 2 3

Radial fuel coordinate (mm)

4

b)

Fig. C-2.3. (a) Axial Distribution of U23-5 Uwls, Pu239, Pu'24 Isotopes and (b) Radial Distribution

of U235 Isotope for Fuel Rod #H2T (calculated)

C-25
#H2T 'actetcs Ro-s4 -eariaedFe ' 'F ~ dd~k++~

S

1a3r

-aS

.no

1.2

1.0

0.8

0.6

0.4

-I. T

puD9

4

v

_ -_ I , _-

2

I, 1 ,, 'I - -!

. .. ''. 't

9X. i -{;

So.'.'-,.

3 ' F .,

;^m

..} ....

.. ... .

........

.. ;. . .

02 _-

I

I 3

Radial fuel coordinate (mm)

4

1) _..- . -

E

2 1.0

r- 0.8 U

.2=0.6

V

8 0.4

U

Fs

Z 0.2

Pe,'

4 + U..-

I .4-

Iv

I .1. - 141--

I

II

A' o :-:' .

,i .. %,.>,

, .?-.-. ., S .

r $ i f

eN;s'm4S'

. .2 ., ,, . <

_sb '; t;t S s _ t_ 'rP

. t

i 3

9

4

Radial fuel coordinate (mm)

Fig. C-2.4. Radial Distribution of Pu239, Pu241 Isotopes for Fuel Rod #112T (calculated)

C-26
#H2T I MBr'nit, haracter16 ics lo~f Rca~brctdFelRd.

mm e ZPiirrdiatedcladdhn)W ~ A~~

l 1.2

,E 1.0 C4

E 0.8

0

C 0.6

.2

B4)

ok 0.4

c) =

:0 2

Z 1 0.2

1 2 3 4

a) Radial fuel coordinate (mm)

1.2

IL

4)

la

2

cd

2

C.)

0.

1.0

0.8

0.6

-t I- ml,-

-, 4-

-I- I

_

0.4 -I-

4--

II

-a, !.s' r

.,

N ,1 , . i ,.E , t ., .

'- -'- '''''

. In--, ha Pa

?':: 't: . _ fs ,.

: .;' - A:: . In

4. -a >,

l:

IV

0.2 +-

I 2 3 4

b) Radial fuel coordinate (mm)

Fig. C-2.5. (a) Radial Distribution of U" 8Isotope and (b) Burnup for Fuel Rod #H2T (calculated)

C-27

C-29
#H3T Refabricd ncaef Fuel R ds

1 lrti; red ; cladding') 't\i- : a -,$ . . '.' _ -' I

Table C-3.1. Axial Distribution of Isotopic Composition for Fuel Rod #H3T (calculated)

Axial coordinate Nuclear concentrations

from lower end (kg/t U)

of fuel rod

(mm) U2

35 I U236 I U238 I pU239 I pu240 I PU24

' I PU242

20

25

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

165

170

175

180

4.68

4.68

4.68

4.84

4.87

5.09

5.09

5.23

5.23

5.20

5.17

5.03

5.01

4.87

4.84

4.68

4.66

4.55

4.55

4.55

4.55

4.50

4.50

4.50

4.50

4.47

4.50

4.68

4.58

4.58

4.58

4.58

4.94

4.94

4.94

4.92

4.92

4.90

4.90

4.89

4.89

4.89

4.89

4.91

4.91

4.92

4.92

4.94

4.94

4.95

4.95

4.95

4.95

4.95

4.95

4.95

4.95

4.95

4.95

4.94

4.95

4.95

4.95

4.95

927

927

927

928

928

929

929

929

929

929

929

928

928

928

928

927

927

927

927

927

927

927

927

927

927

927

927

927

927

927

927

927

4.92

4.92

4.92

4.94

4.94

4.98

4.98

5.01

5.01

5.00

5.00

4.97

4.97

4.94

4.94

4.92

4.91

4.89

4.89

4.89

4.89

4.88

4.88

4.88

4.88

4.87

4.88

4.92

4.90

4.90

4.90

4.90

2.64

2.64

2.64

2.62

2.62

2.59

2.59

2.57

2.57

2.58

2.58

2.60

2.60

2.62

2.62

2.64

2.64

2.65

2.65

2.65

2.65

2.66

2.66

2.66

2.66

2.66

2.66

2.64

2.65

2.65

2.65

2.65

1.588

1.588

1.588

1.583

1.582

1.578

1.578

1.576

1.576

1.577

1.577

1.579

1.579

1.582

1.583

1.588

1.588

1.589

1.589

1.589

1.589

1.589

1.589

1.589

1.589

1.589

1.589

1.588

1.588

1.588

1.588

1.588

1.046

1.046

1.046

1.020

1.016

0.982

0.982

0.961

0.961

0.965

0.969

0.990

0.995

1.016

1.020

1.046

1.050

1.068

1.068

1.068

1.068

1.076

1.076

1.076

1.076

1.080

1.076

1.046

1.063

1.063

1.063

1.063

All numerical values ofcharacteristics arm presented as average values at the length interval equal to the axial coordinate * 2.5 mm

C-30
AH3T ential of" Rc a e I Rod { i'

MmVt1tf (31 tgww!iradiateWatn).^,-,,i,,;i -

Table C-3.2. Radial Distribution of Burnup (Calculated) and Isotopic Composition with RIM Zone

Indication (Calculated) for Fuel Rod #H3T (average values In fuel rod)

Coordinates of fuel radial zones (mm)

Characteristic I zone 2 zone 3 zone 4 zone

1.2 - 2.811 2.811 - 3A32 3.432 - 3.704 3.704 - 3.790

1. Nuclear concentrations

(kg/t U):

u235 4.85 4.65 4.47 4.34

U236 4.94 4.94 4.94 4.94

933. 930. 918. 884.

Pueg 4.14 4.60 6.19 10.48

Pu240 2.34 2.45 3.12 5.05

pu241 1.274 1.479 2.082 3.712

Pu242 0.813 0.970 1.406 2.591

2. Burnup 45.0 47.9 56.2 78.8

(MWd/kg U)

C-31
#H3T I linitia duaC stIFes of Refabncaied Fuel Rods'j, -. .

| idditig); 5ad`- I 

Table C-3.3. Individual Initial Characteristics for Fuel Rod #H3T (measured)

Axial coordi- Cladding Cladding Fuel mass (g) Linear Free gas Burnup

nate from outer outer (density- fuel volume (MWd/kg U)*

lower end diameter diameter 10.134) g/cml)* mass (mm 3

)05)

of fuel rod at O0 at 900 (g/cm)*

(mm) (mm) (mm)

5

10

15

20')

25

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

-155

160

165

170

1752)

180

9.103

9.104

9.106

9.112

9.109

9.106

9.101

9.103

9.106

9.104

9.094

9.092

9.098

9.104

9.104

9.104

9.101

9.101

9.106

9.109

9.119

9.119

9.122

9.109

9.098

9.104

9.100

9.110

9.115

9.113

9.112

9.106

9.094

9.095

9.103

9.113

9.116

9.112

9.115

9.110

9.106

9.113

9.118

9.124

9.116

9.103

9.100

9.100

9.103

9.106

9.104

9.103

9.106

9.112

9.113

9.115

0.0

0.0

0.0

0.92

1.16

1.52

2.04

2.01

1.96

1.95

1.96

1.99

2.02

2.03

2.01

1.98

1.97

1.99

2.01

2.05

2.08

2.07

2.06

2.05

2.06

2.08

2.10

2.12

2.14

2.14

2.16

1.84

1.80

1.71

0.63

0.0

0.0

0.0

0.0

3.06

2.32

3.05

4.08

4.02

3.92

3.91

3.93

3.98

4.05

4.07

4.01

3.96

3.95

3.97

4.02

4.10

4.15

4.14

4.12

4.10

4.13

4.16

4.20

4.25

4.29

4.29

4.33

3.68

3.61

3.41

3.15

0.0

8.8

98.9

34.0

143.5

119.9

84.4

33.3

36.2

41.1

42.1

41.1

38.2

-35.2

34.2

36.2

39.2

40.1

38.2

36.2

32.3

29.3

30.3

31.3

32.3

31.3

29.3

27.3

25.4

23.4

23.4

21.4

52.9

56.9

65.7

172.0

114.8

0.0

0.0

49.53)

49.53)

49.53)

48.8

48.8

48.0

47.9

47.5

47.5

47.6

I 47.6

48.2

48.2

48.8

48.8

49.5

49.5

50.0

50.0

49.9

50.0

50.2

50.2

50.1

50.2

50.3

50.2

49.4

49.93)

49.93)

49.93)

49.93)

0.0

' These numerical values ofcharacteristics are presented as average values at the length interval equal to the axial coordinate ± 2.5 mm

I) Initial coordinate of rfuel is 1 1.5 mm 4) Effective density of fuel stack

2) Final coordinate or fuel is 166.5 mm 5) Free gas volume for coordinates 185 - 295 mm

) Average value is presented in Table C.3

C-32
#H3T - - -7 IJ 2 

1

42O

.4

.F

.rZIn

r.

.9

0 50 100 150 200 250.

a) Axial coordinate (mm)

E  7 -- -.7, -7

b)

5. -100

S

U

E

ev

.Bc

4.0

3.0

I

.E

E

0

tn

C's al

2.0

1.0

0 50 100 .150 200 250

c) Axial coordinate (mm)

Fig. C-3.1. (a) Results of y-scanning, (b) Radiography, (c) Axial Fuel Mass Distribution and Axial Free

Gas Volume Distribution for Fuel Rod #1H3T

C-33
#H3T 'l.fjtIfliWdu = soaeRctefabiiid Fuei Rods i|

Icladding - I .W'.> Ii

60

50

40

30 -_ __ -1

0 50 100 1!0 200 250

a) Axial coordinate (mm)

9.4

aI-.

0

b) Axial coordinate (mm)

.E

I..

-U2

0

G)

la

c) . Axial coordinate (mm)

Fig. C-3.2. (a) Axial Burnup Distribution and (b) Results of Profilometry and (c) Eddy-Current

Examination for Fuel Rod #H3T

C-34
~#H3T

10 I I I~ 1000 -

- l &

t

4 -

0

0-

4

E

0

en

C- rS

Ut

z

U 2

8

6

4

Pu239

* . .. ......... . . ........ ..

_ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _U

2 41

0 40 80 120 160

a) Axial coordinate (mm)

800 A

600

400

200

0

2

0.

1.2

4-.

U

0

0

0

4-

z't

UN

1.0

0.8 4-

I

'4 'II'

0.6 -

. . . - .

_. , ,. . _ '!

" _ ',,, _ .

' :.;' : s .. .. '.'-.;

. .:. : , j ',',;:

. . ' ' -

.;-' - ,,- . : . :,.' '

: ''''' 1. ' ' "'"

- ... ".' ' ,.: I'

-; . -- II -:; - .. , -, - . --

. ,- . ; .- ::

! ! .

A....., I,.

. '' i.'- ' ;': .'.'

.,; - , .,

':' ' I ' - ''

. .: . . .

a- ', * '- ' .' '

.' :': .. '' - -''

; i . . ! i

. ::, . .. ,, ;' .

' > . . w - . '; 3 . : - .

_ ,"-' '': '-- f

iii:

A

IV

0.4 -1-

0.2 -I- .. .1. -. .-

2 3

I

4

b) Radial fuel coordinate (mm)

Fig. C-3.3. (a) Axial Distribution of U235, u23, 'Pu 239, P6241 Isotopes and (b) Radial Distribution

of U235 Isotope for Fuel Rod #H3T (calculated)

C-35
#H3T I tiaft___ d 1 SofRefaiicaed Fu4Rod -1

|& . ai ,cladding) j',ln~4' IvX.,,

.E

V)

c

-.i

0

a

-

:3

.2

8o

._ 1 c

c ) -

z La

1.2

1.0

0.8

0.6

0.4

0.2

Pu239

i

I

:' V

I

II

I

- " , T-,  

I

J-.,-,-

1::'. ,-i .1 ; '',

.. - .. *I

1 2

3

3

I

4

Radial fuel coordinate (mm)

2

2

U

£

0

. . V

c

C.)

O ._

lu cv -45

1.2

1.0

0.8

0.6

0.4

0.2 I .1 1 . I

1 2 . 3 4

Radial fuel coordinate (mm)

Fig. C-3.4. Radial Distribution of Pu239, Pu24 ' Isotopes for Fuel Rod #H3T (calculated)

C-36
fH3T I ninii ceitics of Ref1abrcatcd Fiel Rods - +;

1e,.ad taie zraatedcladding) -S t *I ;j2t

. q ~I.L

.9 E1.0

9.)

nC 1.0

0

r 0.6

4-.

U

U

r. 0.6

.2

o _0.4 _ .

c) , cU L.

Z ac" v.Z.

a) Radial fuel coordinate (mm)

1.2

ECr

0.

4-

0.

-

E

1.0

0.8

0.6

0.4

0.2

b) Radial fuel coordinate (mm)

Fig. C-3.5. (a) Radial Distribution of U2m Isotope and (b) Burnup for Fuel Rod #H3T (calculated)

C-37

dual Characer

-

..... ... ; , ,. .. a > . i . - .... e ,.,; f

; r ,, i,,, a, ; '.1: . ,, ;, .

, _, % . i > w i E, ,¢ Y; ............................. . *' i Ad A.. ........ .. . t 5 .. _ - . s., i- -. j _ ,. . Jo e . < :. i

., .. ,' -:,;: c a, ' ' ' ' 5 ; j ', - w _ .'i !,,',- At ,, '

ivei--R2XAiT

t < -s _ ; i, , t , ,,,, w ;-N

..... ..... .. 9 e . }

C-39
#H4T Initial Individual Charicteristics of Refabricated Fuel Rods - -

(Preirradiated fuel, Mgdiated cladding) - - . .:

Table C-4.1. Axial Distribution of Isotopic Composition for Fuel Rod #H4T (calculated)

Axial coordinate Nuclear concentrations

from lower end (kg/t U)

of fuel rod

(mm) u2 3 5 U 23 6 1 U238 pu239 I pu2 40 I pu 24

1 I Pu 242

10

15

20

25

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

165

4.91

4.91

4.91

4.91

5.24

5.15

5.13

5.04

5.02

5.10

5.13

5.13

5.13

5.35

5.43

5.46

5.49

5.40

5.37

5.46

5.49

5.43

5.37

5.18

5.10

5.04

5.02

4.96

4.91

5.02

5.07

4.91

4.93

4.93

4.93

4.93

4.91

4.91

4.92

4.92

4.92

4.92

4.92

4.92

4.92

4.90

4.89

4.89

4.88

4.89

4.89

4.89

4.88

4.89

4.89

4.91

4.92

4.92

4.92

4.93

4.93

4.92

4.92

4.93

927

927

927

927

928

927

927

927

927

927

927

927

.927

928

928

928

928

928

928

928

928

928

928

927

927

927

927

927

927

927

927

927

5.12

5.12

5.12

5.12

5.17

5.15

5.15

5.14

5.14

5.15

5.15

5.15

5.15

5.19

5.20

5.21

5.21

5.20

5.19

5.21

5.21

5.20

5.19

5.16

5.15

5.14

5.14

5.13

5.12

5.14

5.14

5.12

2.68

2.68

2.68

2.68

2.65

2.66

2.66

2.67

2.67

2.66

2.66

2.66

2.66

2.63

2.62

2.62

2.61

2.63

2.63

2.62

2.61

2.62

2.63

2.65

2.66

2.67

2.67

2.68

2.68

2.67

2.67

2.68

1.657

1.657

1.657

1.657

1.647

1.649

1.650

1.654

1.655

1.651

1.650

1.650

1.650

1.645

1.643

1.643

1.642

1.644

1.645

1.643

1.642

1.643

1.645

1.649

1.651

1.654

1.655

1.657

1.657

1.655

1.652

1.657

1.047

1.047

1.047

1.047

0.997

1.009

1.013

1.026

1.030

1.018

1.013

1.013

1.013

0.980

0.968

0.964

0.959

0.972

0.976

0.964

0.959

0.968

0.976

1.005

1.018

1.026

1.030

1.039

1.047

1.030

1.022

1.047

All numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate ± 2.5 mm

C-40
#H4T lnitiaiIidividuaalChamcteristics of Refabricated Fuel Rods". -

.(Preirradiat treirradiated cladding), . ~ .1- I;., . I-.- -

Table C4.2. Radial Distribution of Burnup (Calculated) and Isotopic Composition with RIM Zone

Indication (Calculated) for Fuel Rod #H4T (average values in fuel rod)

Coordinates of fuel radial zones (mm)

Characteristic I zone 2 zone* 3 zone 4 zone

1.2 - 2.811 2.811 - 3.432 3.432 - 3.704 3.704 - 3.790

1. Nuclear concentrations

(kg/t U):

U235 5.28 5.07 4.87 4.74

U236 4.92 4.92 4.92 4.92

U23s933. 930. 917. 884.

PU239 4.32 4.81 6.48 10.99

Pu240 2.36 2.47 3.16 5.12

pu241 1.320 1.536 2.168 3.872

Pu242 0.790 0.944 1.370 2.526

2. Burnup 44.5 47.3 55.6 77.9

(MWd/k-g U)

C-41
H4T Initial Individuil Characteristics of Refabricated Fuel Rods, :' |

(Peirradiated fuetj5'iFdiated cladding) -., ; < > | 'I 

Table C-4.3. Individual Initial Characteristics for Fuel Rod #H4T (measured)

Axial coordi- Cladding Cladding Fuel mass (g) Linear Free gas Burnup

nate from outer outer (density- fuel volume (MWd/k-g U)*

lower end diameter diameter 10.134) g/cm3 )* mass (mm3 )U)

of fuel rod at 0° at 900 (glcm)*

(mm) (mm) (mm)

5

1 0'

15

20

25

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

1652)

170

175

180

9.102

9.108

9.113

9.114

9.108

9.101

9.102

9.114

9.126

9.125

9.126

9.128

9.116

9.110

9.096

9.105

9.119

9.113

9.104

9.099

9.111

9.122

9.128

9.119

9.107

9.110

9.119

9.128

9.108

9.108

9.108

9.108

9.110

9.104

9.095

9.078

9.076

9.090

9.090

9.087

9.088

9.095

9.098

9.091

9.087

9.087

9.093

9.098

9.093

9.082

9.078

9.091

9.098

9.104

9.102

9.102

0.0

0.10

0.65

1.17

1.21

2.07

2.08

2.05

2.04

2.02

2.01

2.02

2.04

2.06

2.09

2.12

2.12

2.08

2.06

2.06

2.07

2.06

2.08

2.08

2.06

2.02

1.99

1.98

1.96

1.95

1.95

2.01

1.56

0.0

0.0

0.0

0.0

1.03

1.29

2.33

2.43

4.15

4.16

4.10

4.08

4.04

4.02

4.03

4.08

4.12

4.17

4.24

4.24

4.15

4.13

4.13

4.14

4.13

4.16

4.16

4.11

4.04

3.99

3.95

3.91

3.91

3.90

4.03

3.88

0.0

'0.0

0.0

8.8

89.1

170.1

118.9

114.9

30.3

29.3

32.3

33.3

35.2

36.2

35.2

33.3

31.3

28.3

25.4

25.4

29.3

31.3

31.3

30.3

31.3

29.3

29.3

31.3

35.2

38.2

39.2

41.1

42.1

42.1

36.2

80.5

234.0

234.0

114.8

49.6 3

49.60

49.6 3

49.6 3

48.4

48.6

48.7

.49.0

49.1

48.9

48.8

48.7

48.7

47.9

47.6

47.5

47.5

47.7

47.8

47.5

47.4

47.7

47.8

48.6

48.9

49.1

49.1

49.4

49.5

49.1

49.0

49.5

0.0

0.0

0.0

* These numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate 2.5 mm

1) Initial coordinate of fuel is 11.5 mm

2) Final coordinate or fuel is 166.5 mm

3) Average value

4) Effective density of fuel stack

5) Free gas volume for coordinates 185 -295 mm

is presented in Table C.3

C-42
#H4T Initial IndiAMat~haracteristics of Refabricated Fuel Rods - eirradiaied -~erai~ cladding) ::" .:; '.

C)

0 50 100 150 200 250

a) Axial coordinate (mm)

b)

5.0

4.0

100

L

E

U

E

za

2

r4

3.0

2.0

E

*E

es

>1

0

In

C1

0

1.0

0

0 50 100 -150 200 250

c) Axial coordinate (mm)

Fig. C-4.1. (a) Results of y-scanning, (b) Radiography, (c) Axial Fuel Mass Distribution and Axial Free

Gas Volume Distribution for Fuel Rod #H4T

C-43
#H4T Initial Individual Ceteristics of Refabricated Fuel Rods 1

I (Preirinradiated f cladding) : -;-. : - I

to

CE

m

60

50

40

30

0 50 100 150 ' 200 250

a) Axial coordinate (mm)

9.4

IU

0

to

*0

la

0 50 100 150 200 250

b) Axial coordinate (mm)

C,

CA

(4-

0

O

la

c) Axial coordinate (mm)

Fig. C-4.2. (a) Axial Burnup Distribution and (b) Results of Profilometry and (c) Eddy-Current.

Examination for Fuel Rod #H4T

C-44
#H4T Initial Id tCharacteristics of Refabricated Fuel Rods . |

(PreirradTiulPreirradiated cladding) ' -' i : I

10

I.)

z

-a

74

F

r~

>

E

4-

0

M

c

V

8

6

4

2

0

'U23 9

PU241

0 40 80 120 160

a) Axial coordinate (mm)

U235

JIV

' '- ,',- -;'. Ik-. 

1000

5

800

C4 -

4

0

600

400 o

C.)

I200 0

0

1.2

E

E

9 1.0

+~ 0.8

g

a

0

*= 0.6

0

' 0.4

0

C.)

I-._

U c

= , 0.2

1 2 3

Radial fuel coordinate (mm)

4

b)

Fig. C-4.3. (a) Axial Distribution of U235,) U23.89 Pu2399 PU241 Isotopes and (b) Radial Distribution

of U235 Isotope for Fuel Rod #H4T (calculated)

C-45
#H4T Initial Individual Ci~ideristics of Refabricated Fuel Rods ..

| (Preirmdiated fuetWediated cladding) . ' ' '

E

.Pa

3

0

0

0

.E

0

no

2

C

0

Q

.9

0

0

t.°

0 U .

U .

-s c U,-.

n I 

Z^

1.2

1.0

0.8

0.6

0.4

0.2

1.2

1.0

0.8

0.6

0.4

0.2

Pu239

IIV

2 3 4

Radial fuel coordinate (mm)

pU241

. ^ niv

I Z j 4

Radial fuel coordinate (mm)

Fig. C-4.4. Radial Distribution of Pu239, Pu241 Isotopes for Fuel Rod #114T (calculated)

C-46
#H4T Initial TndMjruamharcteristics of Rdfabricated Fuel Rods ':

cn

C.c

0

-.

oE

O

C)

Z- -

1.2

1.0

u 2

__

0.8 1

0.6 --

I I

I

4

KI I

II III

IV

0.4 -

0.2 - _ _. . .

1

I 2

S

3

I

a) Radial fuel coordinate (mm)

1.2

I.-

c

4-.

C)

0.

E

m

1.0

0.8

0.6 i -

0.4 - A..

0.2 I

2

. I

I 3 4

b) Radial fuel coordinate (mm)

Fig. C-4.5. (a) Radial Distribution of U238 Isotope and (b) Burnup for Fuel Rod #H4T (calculated)

C-47

- ^ -

APPEIVD

- 'I Iual Charac4'i Rod?1

C-49
#H5T |Initial Individual C e-ristics of Refabricated Fuel Rods ,. |

(Preirradiated fuele cladding) .- .iated .

Table C-5.1. Axial Distribution of Isotopic Composition for Fuel Rod #H5T (calculated)

Axial coordinate Nuclear concentrations

from lower end (kglt U)

of fuel rod

(mm) U235 I U236 I U238' I pU239 I PU240 I PU241 I Pu242

20

25

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

165

* 170

5.41

5.41

5.41

5.41

5.72

5.75

5.69

5.52

5.47

5.27

5.27

5.27

5.27

5.41

5.30

5.09

5.01

4.86

4.83

4.81

4.91

5.14

5.04

4.81

4.91

5.09

5.19

5.14

5.14

5.14

4.90

4.90

4.90

4.90

4.87

4.87

4.87

4.89

4.89

4.91

4.91

4.91

4.91

4.90

4.91

4.93

4.93

4.95

4.95

4.95

4.94

4.92

4.93

4.95

4.94

4.93

4.92

4.92

4.92

4.92

927

927

927

927

928

928

928

928

927

927

927

927

927

927

927

926

926

925

925

925

926

926

926

925

926

926

927

926

926

926

5.31

5.31

5.31

5.31

5.36

5.67

5.36

5.33

5.32

5.29

5.29

5.29

5.29

5.31

5.29

5.27

5.25

5.22

5.21

5.21

5.23

5.28

5.26

5.21

5.23

5.27

5.28

5.28

5.28

5.28

2.67

2.67

2.67

2.67

2.63

2.62

2.63

2.65

2.66

2.69

2.69

2.69

2.69

2.67

2.68

2.71

2.72

2.74

2.74

2.74

2.73

2.70

2.71

2.74

2.73

2.71

2.69

2.70

2.70

2.70

1.689

1.689

1.689

1.689

1.680

1.679

1.681

1.686

1.687

1.692

1.692

1.692

1.692

1.689

1.691

1.700

1.701

1.703

1.703

1.703

'1.702

1.699

1.701

1.703

1.702

1.700

1.696

1.699

1.699

1.699

0.991

0.991

0.991

0.991

0.946

0.942

0.950

0.975

0.983

1.012

1.012

1.012

1.012

0.991

1.007

1.041

1.053

1.079

1.083

1.087

1.070

1.032

1.049

1.087

1.070

1.041

1.024

1.032

1.032

1.032

All numerical values orcharacteristics are presented as average values at the length interval equal to the axial coordinate OF 2.5 mm

C-50
#H5T I Initial Tndi~fuhil Characteristics of Refabricated Fuel Rods

(Preirradial reirradiated cladding) m ITable C-5.2. Radial Distribution of Burnup (Calculated) and Isotopic Composition with RIM Zone

Indication (Calculated) for Fuel Rod #H5T (average values in fuel rod)

Coordinates of fuel radial zones (mm)

Characteristic I zone 2 zone 3 zone 4 zone

1.2 - 2.811 2.811 - 3.432 3.432 - 3.704 3.704 - 3.790

1. Nuclear concentrations

(kg/t U):

U2" 5.35 5.13 4.94 4.81

u236 4.92 4.92 4.92 4.92

u238 933. 929. 917. 883.

PU239 4.43 4.93 6.64 11.27

Pu240 2.39 2.51 3.19 5.16

Pu241 1.356 1.579 2.229 3.980

Pu242 0.799 0.955 1.386 2.552

2. Burnup 44.7 47.6 56.0 78.6

(MWd/kg U)

C-51
#H5T I Initial Individuil Charateristics of Refabricated Fuel Rods,. .

| (PreiffadiateW fue iadiated cladding) - . - . - |

Table C-53. Individual Initial Characteristics for Fuel Rod #1H5T (measured)

Axial coordi- Cladding Cladding Fuel mass (g) Linear Free gas Burnup

nate from outer outer (density- fuel volume (MWd/k-g U)*

lower end diameter diameter 10.134) g/cm3

)* mass (mm3 )Y5

of fuel rod at 0° at 900 (g/cm)*

(mm) (mm) (mm)

5

10

15

20

25')

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

165

170

175

1802)

9.092

9.088

9.081

9.078

9.088

9.091

9.080

9.081

9.080

9.086

9.092

9.091

9.080

9.080

9.091

9.097

9.088

9.081

9.075

9.078

9.086

9.095

9.091

9.083

9.092

9.095

9.080

9.066

9.078

9.074

9.081

9.083

9.075

9.074

9.072

9.078

9.075

9.072

9.066

9.066

9.075

9.081

9.074

9.072

9.071

9.080

9.080

9.080

9.077

9.089

9.089

9.089

9.080

9.074

9.080

9.104

0.0

0.0

0.0

0.0

1.71

1.19

1.33

1.64

2.20

2.27

2.24

2.15

2.03

1.99

1.85

0.93

0.91

2.15

2.11

2.07

2.04

2.01

2.00

2.01

2.01

2.01

2.02

2.02

2.03

2.05

2.08

1.73

1.11

1.13

1.47

0.54

0.0

0.0

0.0

0.0

3.81

2.38

2.65

3.29

4.39

4.54

4.47

4.30

4.06

3.98

3.70

1.87

1.81

4.30

4.23

4.14

4.08

4.01

4.00

4.01

4.02

4.02

4.04

4.05

4.06

4.09

4.15

3.46

2.22

2.26

2.93

3.63

8.8

98.9

234.0

234.0

65.7

116.9

103.1

72.6

17.5

10.6

13.6

22.4

34.2

38.2

52.0

142.5

144.5

22.4

26.4

30.3

33.3

36.2

37.2

36.2

36.2

36.2

35.2

35.2

34.2

32.3

29.3

63.8

124.8

122.8

89.4

61.7

47.33)

47.33)

47.33)

47.33)

46.2

46.1

46.3

46.9

47.1

47.83)

47.83)

47.83)

47.83)

47.3

47.7

48.5

48.8

49.4

49.5

49.6

49.2

48.3

48.7

49.6

49.2

48.5

48.1

48.33)

48.33)

48.3 3

48.33)

48.3 3 -n .L

* These numerical values orcharacteristics are presented as average values at the length interval equal to the axial coordinate i 2.5 mm

2) Initial coordinate of fuel is 23.0 mm

2) Final coordinate orfuel is 179 mm

3) Average value

) Effective density offuel stack

5) Free gas volume for coordinates 185 -295 mm

is presented in Table C.3

C-52
#H5T Initial Indiv 6TCharacteristics of Refabricated Fuel Rods .

I (Preirradiatg1ifAPreirradiatod cladding) - - I .- - I

0.n

0 50 100 150 200

a) Axial coordinate (mm)

250

Wi it*_NEE

b)

U

E

4)

il

'E

03

41

0 50 . 100 150 200 250

c) . Axial coordinate (mm)

Fig. C-5.1. (a) Results of y-scanning, (b) Radiography, (c) Axial Fuel Mass Distribution and Axial Free

Gas Volume Distribution for Fuel Rod fI5T

C-53
#H5T Initial Indsidual MMeristics of Refabricated Fuel Rods .

(Preirradiated 1ue Janaiated cladding) .: -9

to

:9

60-

50

40 - _OO -50 200 250

30- -

A 5 100 150 21 5

a) Axial coordinate (mm)

9.4

c

rt.

a>

S.

I0

10

I0

a)

la

9.3

9.2

9.1

9.0

b) Axial coordinate (mm)

1.0

0.5

0.0

-0.5

-1.

c) . Axial coordinate (mm)

Fig. C-5.2. (a) Axial Burnup Distribution and (b) Results of Profilometry and (c) Eddy-Current

Examination for Fuel Rod #H5T

C-54
#H115T

10

-)

4-

0

w

C

0

C)

U0

U

I-. C)

z

8

6

4

2

'IDitial !ndiviautV~haracteristics of Refabricated Fuel Rods

(Preirradia(t&T rciadiated cladding)

- 1000

-800 b

pU23 - 600

....u.. 30

.400

200 Z

.. ,. ................. -U2u

400

0

0 40 80 120 160

a) Axial coordinate (mm)

1.2

U)

E

.E

9

C)

0

.E

C

0

C,

c0

o

1- ._:

( c1

Z5 4

:t la

1.0

0.8

0.6

0.4

0.2

u235

1⁄4 I II, IV

- - I IA

i 4

' Radial fuel coordinate (mm)

It

b)

Fig. C-5.3. (a) Axial Distribution of U235, U238, PU2399 pU241 Isotopes and (b) Radial Distribution

of U235 Isotope for Fuel Rod #H5T (calculated)

C-55
#H5T Initial Individual d I-stics of Refabricated Fuel Rods a ^ |

| (Preirradiated fuel cladding) ;iated . -

C)

0

.2

0

1.2

1.0

0.8

0.6

0.4

0.2

1.2

1.0

0.8

0.6

0.4

0.2

_ . ,Pu 9

_ .23I

lv

2 3 4

Radial fuel coordinate (mm)

Pt?,

_ I.l

7;s :.s" --., ,- ....... ,17 Z.;;.,.X... .- .~~~~~~' AS.... .-.. ......

I 4 3

Radial fuel coordinate (mm)

Ct

Fig. C-5.4. Radial Distribution of Pu 3

9, Pu24

1 Isotopes for Fuel Rod #115T (calculated)

C-56
#H5T | Initial Indiivo!-F Chatedisics of Refabricated Fuel Rods i |

I eirradiat JPreirnidiated cladding) . - ... -

Ei

0

0

0

I.-

C31

DC.)

1.2

1.0

i i -.. _ _ _ _ _

-

0.8 ----

0.6 -

Ii -

II III

_ r

jky

L

0.4 I0.2 I I I

1 2 3 4

a) Radial fuel coordinate (mm)

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ I _ _ _ _ _ _ _ _ _ _ I_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 

I

1.2

IC

la

0. 6

2

I n

0.8 -

0.6 -

0.4 -

I 4-

. ;-.-- i. ;; .-....

. , , - , .; . .

--

- .

,.:;. -

.;

. . .

* ,:, .

. .. .

-. . ;

. . . . - . .

III

lV

0.2 -_- .

l

2

l

3 4

b) Radial fiel coordinate (mm)

Fig. C-5.5. (a) Radial Distribution of U238 Isotope and (b) Burnup for Fuel Rod #115T (calculated)

C-57

AndA PP ~vS * o ,,.,:P ''"^ '"'o''s"" 1

" '-i At'',* '''.- -' be,, ', .'z, 'I: Its" .'.. I

a e a; < r 1 - v v f A |

.g.u.el.>..R W)Jt; l ; 

* S 

; 

S z 

t 

. ; v K r ; at t 7; s > I . . s.- . ' .. a 

-

. i S -. .!f!l i< ^ . i - - -

C-59
#H6T Initial Individual Chardteristics of Refabricated Fuel Rods :

(Preirradiated fuel,,a,>iated cladding) -

Table C-6.1. Axial Distribution of Isotopic Composition for Fuel Rod #H6T (calculated)

Axial coordinate Nuclear concentrations

from lower end (kg/t U)

of fuel rod

(mm) U2 " I U2 U238 I Pu239 | Pu 24 0 I pU24 1 I Pu 242

15

20

25

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

165

170

175

180

5.35

5.35

5.35

5.35

5.21

5.21

5.15

5.15

5.15

5.15

5.15

5.15

5.15

5.15

5.15

5.15

5.15

5.15

5.07

5.10

5.10

4.83

4.81

4.60

4.83

4.83

4.83

4.83

4.83

4.83

4.83

4.83

4.83

4.83

4.90

4.90

4.90

4.90

4.91

4.91

* 4.91

4.91

4.91

4.91

4.91

4.91

4.91

4.91

4.91

4.91

4.91

4.91

4.92

4.92

4.92

4.94

4.94

4.96

4.94

4.94

4.94

4.94

4.94

4.94

4.94

4.94

4.94

4.94

928

928

928

928

927

927

927

927

927

927

927

927

927

927

927

927

927

927

927

927

927

926

926

925

926

926

926

926

926

926

926

926

926

926

5.19

5.19

5.19

5.19

5.16

5.16

5.15

5.15

5.15

5.15

5.15

5.15

5.15

5.15

5.15

5.15

5.15

5.15

5.14

5.15

5.15

5.11

5.10

5.05

5.11

5.11

5.11

5.11

5.11

5.11

5.11

5.11

5.11

5.11

2.63

2.63

2.63

* 2.63

2.65

2.65

2.66

2.66

2.66

2.66

2.66

2.66

2.66

2.66

2.66

2.66

2.66

2.66

2.67

2.66

2.66

2.69

2.70

2.72

2.69

2.69

2.69

2.69

2.69

* 2.69

2.69

2.69

2.69

2.69

1.645

1.645

1.645

1.645

1.648

1.648

1.649

1.649

1.649

1.649

1.649

1.649

1.649

1.649

1.649

1.649

1.649

1.649

1.652

1.651

1.651

1.658

1.658

1.660

1.658

1.658

1.658

1.658

1.658

1.658

1.658

1.658

1.658

1.658

0.980

0.980

0.980

0.980

1.001

1.001

1.009

1.009

1.009

1.009

1.009

1.009

1.009

1.009

1.009

1.009

1.009

1.009

1.022

1.018

1.018

1.060

1.064

1.099

1.060

1.060

1.060

1.060

1.060

1.060

1.060

1.060

1.060

1.060 _ I I I I

All numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate *t 2.5 mm

C-60
#H6T ' .: .I.

initial lndividifiCharacteristics of Refabricated Fuel Rods ;

I iindiateePrcinadiated cladding)*. . ITable C-6.2. Radial Distribution of Burnup (Calculated) and Isotopic Composition with RIM Zone

Indication (Calculated) for Fuel Rod #1H6T (average values In fuel rod)

Coordinates of fuel radial zones (mm)

Characteristic I zone 2 zone 3 zone 4 zone

1.2 - 2.811 2.811 -3.432 3.432 - 3.704 3.704 - 3.790

1. Nuclear concentrations

(kg/t U):.

u235 4.75 4.55 4.36 4.24

u236 4.94 4.94 4.94 4.94

u23s934. 930. 918. 885.

PU239 4.08 4.53 6.09 10.31

Pu240 2.32 2.43 3.10 5.02

Pu24

1 1.254 1.455 2.047 3.647

Pu242 0.815 0.971 1.406 2.592

2. Burnup 45.1 47.9 56.2 78.7

(MWd/kg U)

C-61
#H6T Initial Individuil Characeristics of Refabricated Fuel Rods;

(Preirradiated fineljOr mdiated cladding) -. .-: . -. I 

Table C-6.3. Individual Initial Characteristics for Fuel Rod #H6T (measured)

Axial coordi- Cladding Cladding Fuel mass (g) Linear Free gas Burnup

nate from outer outer (density- fuel volume (MWdfkg U)*

lower end diameter diameter 10.134) g/cm3 )* mass (mm3 )5)

of fuel rod at 0° at 900 (glcm)*

(mm) (mm) (mm) I I

5

10

20

25

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

165

170

175

1802)

9.110

9.109

9.106

9.103

9.098

9.103

9.101

9.095

9.092

9.100

9.109

9.110

9.113

9.104

9.103

9.107

9.103

9.106

9.106

9.107

9.110

9.112

9.113

9.115

9.116

9.116

9.116

9.127

9.092

9.091

9.100

9.106

9.107

9.100

9.106

9.118

9.131

9.121

9.115

9.107

9.113

9.110

9.106

9.103

9.109

9.118

9.122

9.118

9.113

9.106

9.104

9.101

9.104

9.107

9.110

9.109

0.0

0.0

0.91

1.01

.97

.97

2.09

2.27

1.82

1.05

1.66

1.33

1.10

1.21

2.00

1.30

1.51

1.28

.13

1.00

2.02

2.07

2.08

2.07

2.05

1.97

1.39

1.39

1.33

1.02

1.87

1.86

1.19

1.18

1.01

0.10

0.0

0.0

2.03

2.03

1.94

1.94

4.19

4.53

3.64

2.11

3.32

2.65

2.20

2.41

4.00

2.59

3.02

2.56

.25

2.00

4.05

4.14

4.16

4.13

4.10

3.93

2.79

2.78

2.66

2.04

3.73

3.71

2.38

2.35

2.03

2.00

8.8

98.9

144.5

134.6

138.6

138.6

28.3

10.6

54.9

130.7

70.7

103.1

125.8

114.9

37.2

106.1

85.4

108.1

221.2

135.6

35.2

30.3

29.3

30.3

32.3

40.1

97.2

97.2

103.1

133.6

50.0

51.0

116.9

117.9

134.6

105.0

47.0

47.0

47.0

47.0

47.5

47.5

47.73)

47.73)

47.73)

47.73)

47.73)

47.73)

47.73)

47.73)

47.73)

47.73)

47.73)

47.73)

48.0

47.9

47.9

48.9

49.0

49.8

48.93)

48.93)

48.93)

48.93)

48.93)

48.93)

48.93)

48.93)

48.93)

48.93)

' These numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate ± 2.5 mm

|) Initial coordinate of fuel is 13.0 mm 4) Effective density of fuel stack

2) Final coordinate of fuel is 178 mm

3) Average value

5) Free gas volume for coordinates 185 - 295 mm

is presented in Table C.3.

C-62
#H6T | Initial IndYCbaracteristics of Refabricated Fuel Rods.- |

(Pd cladding) - : - ;-; I -

U)

0.

U)

U2

0 50 100 150 200 250

a) Axial coordinate (mm)

b)

(

E

0

EP

es

0LI

C: 0

U)

r0

S.-A..- ........... ;

I- T I I - -r - -

150 200

c) : Axial coordinate (mm)

0 50 100 250

Fig. C-6.1. (a) Results of y-scanning, (b) Radiography, (c) Axial Fuel Mass Distribution and Axial Free

Gas Volume Distribution for Fuel Rod #H6T

C-63
#H6T Initial Individual ,7;ieristics of Refabricated Fuel Rods I

.(Preirradiated fiic Wiated cladding) -I-: -. .

60

50

40

30

9.4

a) Axial coordinate (mm)

2I0

0

Ie,)

Ud

0Ez

2.

9.3

9.2

9.1

9.0

b) Axial coordinate (mm)

0 50 100 150 200

c) Axial coordinate (mm)

250

Fig. C-6.2. (a) Axial Burnup Distribution and (b) Results of Profilometry and (c) Eddy-Current

Examination for Fuel Rod #H6T

C-64
#H6T Initial Indivi lCharacteristics of Refabricated Fuel Rods~ -

(re ffadi~tMTq:Preiffadiated cladding) ': .; .: ,''' -

10

n

0

0

U

Cs

0

G) z

8

6

4

2

0

PU2

_..... ... .....................................

_ =, |......... ............2

_ _ . .35I 

.. ,'........... ..... ............ ....... ....

Pue,

.0 40 80 120 160

a) Axial coordinate (mm)

_- I .:- III -.

_- ,,* ,D.$ , ;lI 2 ., 1- ,,I .... X'.

1000

800

0

600 -

400 o0

I..

C3

200 Z

0

1.2

9 1.0

U

> 0.8 _.g

*0.6 I

4. 0.4

0

Cs

r_

c) =

= 0.2 za. 1 2 3

- Radial fuel coordinate (mm)

4

b)

Fig. C-6.3. (a) Axial Distribution of U235, Uu 8

, Pu239, Pu24 Isotopes and (b) Radial Distribution

of U"' Isotope for Fuel Rod #116T (calculated)

C-65
#H6T Initial Individual dChteristics of Refabricated Fuel Rods 7 -

(Preirradiated fiueljIiated cladding) -. I

-,E

O

*1

18

0

U4.2

V

1.2

1.0

0.8

0.6

0.4

0.2

1')

Pu239

IV

12 3 4

Radial fuel coordinate (mm)

pu, ,

.'. 1.,,... .

. 1 ::'-; --

_ .. ~~Il:,:-.

_ :',r. - ,, ,'111- .

',.';',',, :'.'4 ', , .3.", ','w j _. ;' l ' ' -'

_E 1.0

£

.2

.£6

E12

2 10

3

- 0.8

0

0.6

U

O 0.4

_ 2

Z- 0

; '0.2

I 2 3 4

Radial fuel coordinate (mm)

Fig. C-6.4. Radial Distribution of Pu239, Pu241 Isotopes for Fuel Rod #I16T (calculated)

C-66
#H6T Initial TndMvCharacteristicsiof Refabricated Fuel Rods , . .

| (Preirradi___i Lrciladiatcd cladding) '. K- - . -

1- 1.2-

-n 1.0- cnU

0.8

0-

c: 0.6 0

4-

o0.4-

c I

c) L

0s 0.2 -

U23 s

I-' _-K

IaL ' -E , <,, , ,s,, . 1, ;s,, .

. - . . -, .... .. : - . f . ....... :;. :: . g -: .- .;

' X - -- Y . . . . -... - .- 'X, -!-.;

. > . ' . ' . C . ,' b ,' , 4 0 ' ...... s

.: a-,- . - . - . ... . . , -, -- - ., - . , . .o,

' ' ' . . ! .; .. |, ... ,, , _ . . .. .

. . ? ,; . . - - - - ;t '" - - > "

' : ' '; .-'';''''!U' - .. ' '' !' ' ' - 8, .- ,. . . i, ; ' _ ..... .

, _: - ' . - . , . . . ., ,, _,, r 2, ..... ,

;''.' ",'" '. ,''',.'' 8 ,"'.-''. ;' 'r' 's-E."''.<:"

.... _ .. _ .. : _ .... ,...: . _ .. :S . _ I i, ...

L L:; : e r:

II IT"

L

IV

.'

X _ E fi

I

2 3

I

4

a) Radial ffuel coordinate (mm)

1.2

0-

C1

0.

C.)

0.

.e

1.0

0.8

0.6

I I. i .

4 -

-1 I

0.4 1 -I II

___________________________ I - I - I -

III

"V

0.2 ., . . . .

I

2

A

I 3 4

b) Radial fuel coordinate (mm)

Fig. C-6.5. (a) Radial Distribution of U238 Isotope and (b) Burnup for Fuel Rod #H6T (calculated)

C-67

A,>,'';PP,..E

fua! Characi

C-69
#H7T Initial Individual Charac-teristics of Refabricated Fuel Rods - -

(Preirradiated ujp gimA~hliated cladding) : : : : : . .- .

Table C-7.1. Axial Distribution of Isotopic Composition for Fuel Rod 4H7T (calculated)

Axial coordinate Nuclear concentrations

from lower end (kg/t U)

of fuel rod

(mm) U2 3 5 I U23 6 U2 3 pu23 9 I pU2 40 I pu 24 1 I pu 242

20

25

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

165

170

175

180

5.89

5.89

5.89

5.89

5.89

5.89

5.80

5.72

5.57

5.57

5.57

5.54

5.49

5.54

5.63

5.60

5.37

5.37

5.37

5.43

5.40

5.35

5.35

5.35

5.35

5.35

5.35

5.35

5.35

5.35

5.35

5.35

5.35

4.84

4.84

4.84

4.84

4.84

4.84

4.85

4.86

4.87

4.87

4.87

4.88

4.88

4.88

4.87

4.87

4.89

4.89

4.89

4.89

4.89

4.90

4.90

4.90

4.90

4.90

4.90

4.90

4.90

4.90

4.90

4.90

4.90

930

930

930

930

930

930

929

929

929

929

929

929

928

929

929

929

928

928

928

928

928

928

928

928

928

928

928

928

928

928

928

928

928

5.27

5.27

5.27

5.27

5.27

5.27

5.26

5.25

5.23

5.23

5.23

5.22

5.21

5.22

5.214

5.23

5.19

5.19

5.19

5.20

5.20

5.19

5.19

5.19

5.19

5.19

5.19

5.19

5.19

5.19

5.19

5.19

5.19

2.57

2.57

2.57

2.57

2.57

2.57

2.58

2.59

2.60

2.60

2.60

2.61

2.61

2.61

2.60

2.60

2.63

2.63

2.63

2.62

2.63

2.63

2.63

2.63

2.63

2.63

2.63

2.63

2.63

2.63

2.63

2.63

2.63

1.627

1.627

1.627

1.627

1.627

1.627

1.630

1.634

1.639

1.639

1.639

1.641

1.642

1.641

1.637

1.638

1.645

1.645

1.645

1.643

1.644

1.645

1.645

1.645

1.645

1.645

1.645

1.645

1.645

1.645

1.645

1.645

1.645

0.903

0.903

0.903

0.903

0.903

0.903

0.915

0.927

0.947

0.947

0.947

0.951

0.959

0.951

0.939

0.943

0.976

0.976

0.976

0.968

0.972

0.980

0.980

0.980

0.980

0.980

0.980

0.980

0.980

0.980

0.980

0.980

0.980 £ L A. .5. 1 .3. 5

All numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate ± 2.5 mm

C-70
1#H7T Initial lnd -a;lCharacteristics of Refabricated Fuel Rods

(reixrad 'Preirradiated _ cladding) :: . --

Table C-7.2. Radial Distribution or Burnup (Calculated) and Isotopic Composition with RIM Zone

Indication (Calculated) for Fuel Rod #1H7T (average values in fuel rod)

Coordinates of fuel radial zones (mm)

Characteristic I zone 2 zone 3 zone 4 zone

1.2 - 2.811 2.811 - 3.432 3.432 - 3.704 3.704 - 3.790

1. Nuclear concentrations

(kg/t U):

U235 5.28 5.07 4.87 4.74

u236 4.89 4.89 4.90 4.90

U"8 935 931 920 888

Pu239 4.15 4.61 6.21 10.56

Pu240 2.26 2.38 3.04 4.96

pu24

1 1.242 1.444 2.038 3.650

Pu242 0.750 0.895 1.299 2.400

2. Burnup 43.4 46.0 53.9 75.1

(MWd/kg U)

C-71
#H7T Initial Individual CShibteristics of Refabricated Fuel Rods -

(Preirradiated fuel- Riadiated cladding) : ; I :;

Table C-7.3. Individual Initial Characteristics for Fuel Rod #1H7T (measured)

Axial coordi- Cladding Cladding Fuel mass (g) Linear Free gas Burnup

nate from outer outer (density- fuel volume (MWd/kg U)*

lower end diameter diameter 10.13') gfcm3 )* mass (mm3 )"5

of fuel rod at O0 at 900 (glcm)*

(mm) (mm) (mm)

S

10

15

20')

25

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

165

170

175

1802)

9.103

9.094

9.094

9.101

9.113

9.112

9.110

9.109

9.112

9.115

9.101

9.092

9.098

9.104

9.110

9.112

9.119

9.122

9.121

9.122

9.122

9.124

9.119

9.119

9.127

9.127

9.124

9.128

9.118

9.124

9.122

9.113

9.118

9.118

9.113

9.112

9.107

9.116

9.124

9.124

9.119

9.121

9.122

9.122

9.118

9.115

9.112

9.110

9.110

9.106

9.104

9.104

9.106

9.106

9.106

9.104

0.0

0.0

0.0

0.45

1.94

1.51

1.64

1.63

1.70

2.15

2.07

2.02

2.01

2.00

2.00

2.06

2.05

2.03

2.04

1.15

.90

1.95

1.99

1.96

1.88

1.79

1.74

1.76

1.80

1.84

1.84

1.82

1.83

1.60

1.20

0.46

'0.0

0.0

0.0

4.50

3.88

3.01

3.29

3.26

3.40

4.30

4.14

4.03

4.02

3.99

4.00

4.11

4.10

4.06

4.08

2.31

1.80

3.90

3.98

3.93

3.77

3.57

3.49

3.52

3.60

3.69

3.67

3.64

3.66

3.20

2.41

2.30

8.8

98.9

234.0

189.7

43.1

85.4

72.6

73.6

66.7

22.4

30.3

35.2

36.2

37.2

37.2

31.3

32.3

34.2

33.3

120.9

145.5

42.1

38.2

41.1

49.0

57.9

62.8

60.8

56.9

52.9

52.9

54.9

53.9

76.6

115.9

69.5

45.13)

45.13)

45.13)

45.13)

45.13)

45.13)

45.4

45.7

46.2

46.2

46.2

46.3

46.5

46.3

46.0

46.1

46.93)

46.93)

46.93)

47.2

46.8

47.03)

47.03)

47.03)

47.03)

47.03)

47.03)

47.03)

47.03)

47.03)

47.03)

47.03)

47 .03)

* These numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate ± 2.5 mm

1

)lnitial coordinate of fuel is 21.5 mm 4) Effective density of fuel stack

2) Final coordinate of fuel is 179.5 mm

3) Average value

5) Free gas volume for coordinates 185 - 295 mm

is presented in Table C.3

.C-72
#H7T |Inidal IndM F:haracteristics of Refabricated Fuel Rods n -

I '(Prcirra ite rradiated cladding) ; -- -

4)

4)

?I0 50 100 150 200

a) Axial coordinate (mm)

250

M

b)

5.0 .IA100

4.0 -

3.0 -

2.0 -

1.0 -

0*

I -....... gasI

1

-80

-60 E

E

e-

_40 Et

. r

ct

. ...

Vii .*.e-J

20

a- - I 1.

I I I I

50 100

I I I I I 0

0 150 200 250

c) . Axial coordinatc (mm)

Fig. C-7.1. (a) Results of y-scanning, (b) Radiography, (c) Axial Fuel Mass Distribution and Axial Free

Gas Volume Distribution for Fuel Rod #1I7T

C-73
#H7T Initial Individald Chia-ristics of Refabricated Fuel Rods -

l (Preirradiated fue&l, iated cladding) .

60

50

40

30 I I A

50 100 50 200 250

a) Axial coordinate (mm)

9.4

Or_

I-

.)

0

*0

rU

0z:

*0

2

b) Axial coordinate (mm)

c) Axial coordinate (mm)

Fig. C-7.2. (a) Axial Burnup Distribution and (b) Results of Profilometry and (c) Eddy-Current

Examination for Fuel Rod #H7T

C-74
#H7T rirradziiuPreirradiated cladding)

10

fl

0

'1)

n

0

U

z

8

6

4

2

0

u238

'P '_;9

u235

Pu24

1

0 40 80 120 160

a) Axial coordinatc (mm)

U235

IILI J> IV

1000

800 i

Z6

E

0

600

8

400 rU

I.. 0

200

0

1.2

._

es

u

9

U

0

U-

.v

0 -,

Z3

1.0

0.8

0.6

0.4

0.2

1 2 3 .4

b) Radial fuel coordinate (mm)

Fig. C-7.3. (a) Axial Distribution of U235

, U"8 , Pu239, Pu241 Isotopes and (b) Radial Distribution

of U235 Isotope for Fuel Rod #H7T (calculated)

C-75
#H7T Initial Tndividunl C~mri istics of Refabricated Fuel Rods . -

(Preirradiited fiueL cladding) ]jiurjdiated - - -.::I..- .

E

.E

Q

0.

0

C)

C

0

o 4-._

- S

U- C

ES

1.2

Pu 2

3

1.0

0.8

0.6

0.4

0.2

1.2

1.0

0.8

0.6

0.4

0.2

2 3 4

Radial fucl coordinate (mm)

Pun'

- r-+ ; | . . ~ -

I

I

2 - 3

I

4

Radial fuel coordinate (mm)

Fig. C-7.4. Radial Distribution of Pu239

, Pu241 Isotopes for Fuel Rod #H17T (calculated)

C-76
4H7T Initial IndM~ria haracteristics of Refabricated Fuel Rods . .

:(PteinraQ 0 ei reiriadiated cladding) : I| : 1 : 

Cs

U

0

C)

0

0

o_

IeC )

1.2 -

1.0 -

0.8 -

0.6 -

Urn

.'_ '' ' . . .' ' ' ' ' . , ' - . h.. :

_ ' ;':t' ' .' ' ' ' . ' ' . " s ' . ' . o.'" ' '''A'Mv . '

,; ,. . . , _; , , ,, '., !, _ ,_. ._ . l . ..

< $' '. '' ', ' '.'.. ' .- '' ', ' ',,.t'. ._

> * * , ', _',,' ' '' ;,,; ,4 ;, -,

t',,',. g .. ''-,;

.. ,.. ,,; ,", ,' ;,'_,,," ,; '.' .. "; '..''

. ', '' ^ . ' '. ",' ,''-"'', 'te.' '-:''.<.

: ,- ' . ' ., '' '' - ",>. ' . ' .-''; ' . _', . ',_ <',

' ,." "'s ' . . ', < ', ' .: ''; i ' '. .' , .:;,.

..':', ' ','' ' '., '- '' " "'.;; ; "'.',..'. '..

, -, ,:'.' , ' ',', - - -s ., ., ,,,, ., '., _ .4 ,, ' .,. _', . _.

. <.: _. ' ' . . .' '. :' ;.';'.' .: ' . .,.',.; ',,

JI IM.

L

IV

0.4 -

0.2 _ _ . . ..

T __

i T

2

I

3

I

I 4

a) Radial fuel coordinate (mm)

1.2

I.-

4-.

el

1.0 -

0.8 -

0.6 -

0.4 -

I 4

I + 4

_ -I

l

I II

Ill

k

"IV

0.2 -_ -.. .

2 3

I

4

b) Radial fuel coordinate (mm)

Fig. C-7.5. (a) Radial Distribution of U23"8 Isotope and (b) Burnup for Fuel Rod f#H7T (calculated)

C-77

4 -

'nel RodH8Pb.>.

C-79
#H8T Tnitial Individual Cfi~le-istics of Refabricated Fuel Rods -. I

(Preirradiated fiel idiated cladding)

Table C-8.1. Axial Distribution of Isotopic Composition for Fuel Rod #H8T (calculated)

Axial coordinate Nuclear concentrations

from lower end (kg/t U)

of fuel rod

(mm) U2

35 I U236 I U238 I PU239 I pU240 I pu241 I PU242

10

15

20

25

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

165

170

175

5.50

5.50

5.50

5.50

5.50

5.50

5.50

5.50

5.50

5.50

5.50

5.50

5.50

5.50

5.50

5.50

5.50

5.50

5.50

5.47

5.78

5.89

5.92

5.92

5.78

5.72

5.98

6.10

6.19

6.25

6.55

6.68

6.62

6.62

4.89

4.89

4.89

4.89

4.89

4.89

4.89

4.89

4.89

4.89

4.89

4.89

4.89

4.89

4.89

4.89

4.89

4.89

4.89

4.89

4.87

4.85

4.85

4.85

4.87

4.87

4.85

4.83

4.82

4.82

4.79

4.77

4.78

4.78

928

928

928

928

928

928

928

928

928

928

928

928

928

928

928

928

928

928

928

927

928

929

929

929

928

928

929

929

930

930

931

931

931

931

5.33

5.33

5.33

5.33

5.33

5.33

5.33

5.33

5.33

5.33

5.33

5.33

5.33

5.33

5.33

5.33

5.33

5.33

5.33

5.32

5.37'

5.39

5.39,

5.39

5.37

5.36

5.40

5.41

5.42

5.43

5.47

5.49

5.48

5.48

2.66

2.66

2.66

2.66

2.66

2.66

2.66

2.66

2.66

2.66

2.66

2.66

2.66

2.66

2.66

2.66

2.66

2.66

2.66

2.66

2.62

2.61

2.60

2.60

2.62

2.63

2.60

2.58

2.57

2.56

2.52

2.51

2.51

2.51

1.686

1.686

1.686

1.686

1.686

1.686

1.686

1.686

1.686

1.686

1.686

1.686

1.686

1.686

1.686

1.686

1.686

1.686

1.686

1.687

1.677

1.672

1.671

1.671

1.677

1.680

1.669

1.664

1.660

1.657

1.645

1.638

1.641

1.641

0.979

0.979

0.979

0.979

0.979

0.979

0.979

0.979

0.979

0.979

0.979

0.979

0.979

0.979

0.979

0.979

0.979

0.979

0.979

0.983

0.938

0.922

0.918

0.918

0.938

0.946

0.910

0.895

0.883

0.875

0.835

0.819

0.827

0.827

All numerical values orcharacteristics are presented as average values at the length interval equal to the axial coordinate ± 2.5 mm

C-80
#H8T Initial Indtl dCharacteristics of Refabricated Fuel Rods .X

I (Preiftidiai~ Preirradiatedcladding) .: - . I ; - I

Table C-8.2. Radial Distribution of Burnup (Calculated) and Isotopic Composition with RIM Zone

Indication (Calculated) for Fuel Rod #H8T (average values in fuel rod)

Coordinates of fuel radial zones (mm)

Characteristic 1 zone 2 zone 3 zone 4 zone

1.2 - 2.811 2.811 - 3.432 3.432 - 3.704 3.704 - 3.790

1. Nuclear concentrations

(k-g/tU):

u235 5.94 5.72 5.51 5.37

u236 4.86 4.87 4.87 4.88

U238 934 931 919 887

Pu239 4.50 5.01 6.77 11.52

Pu240 2.31 2.44 3.12 5.08

pu241 1.338 1.561 2.210 3.964

Pu242 0.730 0.874 1.271 2.346

2. Burnup 42.8 45.6 53.4 74.6

(MWd/kg U)

C-81
#H8T I 1ziiida'l -1i m o9 f Refabkicaied Fuel Rawi " , 

| Preri. ;dS1 cleadding) x i *I t>'v ;

Table C-83. Individual Initial Characteristics for Fuel Rod #H8T (measured)

Axial coordi- Cladding Cladding Fuel mass (g) Linear Free gas Burnup

nate from outer outer (density- fuel volume (MWd/lkg U)*

lower end diameter diameter 10.13') gfcm3 )* mass (mm3 )'5)

of fuel rod at 00 at 90° (glcm)*

(mm) (mm) (mm) c

5

15

20

25

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

165

170

1752)

180

9.111

9.113

9.116

9.117

9.119

9.113

9.108

9.104

9.107

9.113

9.114

9.111

9.101

9.099

9.107

9.104

9.095

9.088

9.095

9.108

9.105

9.099

9.107

9.119

9.125

9.116

' 9.111

9.108

9.101

9.110

9.117

9.125

9.113

9.105

'9.110

9.122

9.119

9.113

9.111

9.122

9.135

9.128

9.114

9.111

9.114

9.119

9.110

9.102

9.104

9.108

9.107

9.098

9.096

9.102

9.111

9.108

0.0

0.02

0.06

0.34

0.63

1.13

1.65

1.50

1.35

1.33

1.32

1.59

1.85

1.87

1.88

1.85

1.83

1.78

1.72

1.82

1.98

1.99

1.99

1.99

1.98

1.99

2.01

2.04

2.08

2.11

2.13

2.14

2.12

2.08

2.08

0.0

0.0

0.12

0.12

0.69

1.25

2.27

3.29

2.99

2.69

2.67

2.64

3.17

3.69

3.73

3.77

3.71

3.67

3.56

3.45

3.64

3.95

3.99

3.98

3.98

3.97

3.98

4.02

4.08

4.15

4.22

4.25

4.27

4.24

4.15

4.15

0.0

8.8

98.9

234.0

189.7

43.1

85.4

72.6

73.6

66.7

22.4

30.3

35.2

36.2

37.2

37.2

31.3

32.3

34.2

33.3

120.9

145.5

42.1

38.2

41.1

49.0

57.9

62.8

60.8

56.9

52.9

52.9

54.9

53.9

76.6

115.9

0.0

47.93)

47.93)

47.93)

47.93)

47.93)

47.93)

47*93)

47.93)

47.93)

47.93)

47.93)

47.93)

47.93)

47.93)

47.93)

47.93)

47.93)

47.93)

47.93)

48.1

46.9

46.5

46.5

46.4

46.9

47.1

46.2

45.8

45.4

45.3

443

43.8

44.13)

44.13)

0.0

* These numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate ± 2.5 mm

2) Initial coordinate of fuel is 10.5 nun

2) Final coordinate offuel is 177.5 mm

3) Average value

4) Effective density of fuel stack

Free gas volume for coordinates IS5 - 295 mm

is presented in Table C.3

C-82
#H8T nJ~ , hactsIcs'ofRe1rcaceI R. 1.,~ ~~~~~~~" Gus Ais.A.l "Idite Itdi4! if; .I?-a

U)

U);

U)

0 50 100 150 200 250

a) Axial coordinate (mm)

E M

b)

5.0

4.0

I

E

2

.4

3.0

2.0

5

0

U)

1.0

0

0 50 100 150 200 250

c) Axial coordinate (mm)

Fig. C-8.1. (a) Results of y-scanning, (b) Radiography, (c) Axial Fuel Mass Distribution (c) and Axial

Free Gas Volume Distribution for Fuel Rod #118T

C-83
uH8T Ird iA =: f:Li ofReabncaid Fuel Rod*'

lc a d n g Ah So H i '

60

50

40

30 i i I

0 50 100 150 200 250

a) Axial coordinate (mm)

9.4

I-l

to

.E.

a

cR

0 50 100 . .150 200

b) Axial coordinate (mm)

250

c) Axial coordinate (mm)

Fig. C-8.2. (a) Axial Burnup Distribution and (b) Results of Profilometry and (c) Eddy-Current

Examination for Fuel Rod fiH8T

C-84
#H8T

10

)

0-

CE

0

0

C.

U

U

C

8

6

4

2

0

I i lid~ hati C~~edwstcs4Refakbdi cateiIueI Ro

j~diiiI~~n diatcd claddn-)

-. 1000

U 23

800 ~

400

~200 Z

PU241

I - 0

0 40 80 120 160

a) Axial coordinate (mm)

1.2

E

E

0

101

0

't

C

Q

ZS?

U2 M

1.0 -

0.8 -

0.6 -

_ r

;. T , 4 i-'_ . r . . .

_ . - . .. F ., . . _s S -5- 5

, 9: ., -:. .-s ' ' t - [ ', t e ,

L '' ..- '-i '.- '' . -- ,, :,' - /'g N i,;d

''','sA ! P-,-s Ez ]

l .:: .!: . I ..S

| " " ' '! > .. 9 i ' \''' z ' ¢

| f;5_r o ' - !-'';"'-'

| c _, 5 t ,. -| A ! . 1

i . .. !' ' - } > ,' -s |

| i, J S ,"! ._'_',;--;_',".'wb g

1E ;'i-aJ 7' tv ';y, i 71l

2

1

II

_ ., > ,..

. .. _

., ._,6

. .nS .

..-.. .;,:,

f IZ- ... A..,

.::;:! .... ;.

. -: .....

. X,, . .t ,,-. .

. . '..S . ..

'r,..,'.

i.rE ,, t_,*..

IJ

0.4 -1

0.2 -f- i - b - -

1

I

-3 4

b) -Radial fuel coordinate (mm)

Fig. C-8.3. (a) Axial Distribution of U235, U29, Pu 9, Pu241 Isotopes and (b) Radial Distribution

of U235 Isotope for Fuel Rod #II8T (calculated)

C-85
#H8T i FuelREd I

, n dl cladding)> ; ; I 

.E

U

0

.C?

V

c

r-S

c

._

r1.2

1.0

0.8

0.6

0.4

0.2

Radial fuel coordinate (mm)

1-

E

c

U

U

*.9E

0

U

c

0 .

0

C

CU;

Z sl

1.2

1.0

0.8

0.6

.Peu 2

. ;IV

______________-______ ,.,_____ tE -

0.4 - -

0.2 4 -

I

i . Ill

I - I * . -

.'" -' f' '. ', .'- 

r, S., , , f is o. ii". ,; ... ... , .-

I

2 3 4

- Radial fuel coordinate (mm)

Fig. C-8.4. Radial Distribution of Pu239, Pu2

41 Isotopes for Fuel Rod #118T (calculated)

C-86
-H8T a iediatd Oi.dd - 1-: 

S

F.

0

.£

0

a

P.gs

0

-r

.V

:9 .E Ou 2

3 u

Z4

1.2

1.0

0.8

0.6

0.4

0.2

a) Radial fuel coordinate (mm)

1.2

C,

0.

.E

c>

-

U

m.

1.0

0.8

0.6

0.4

0.2

b) 'Radial fuel coordinate (mm)

Fig. C-8.5. (a) Radial Distribution of U2-3 Isotope and (b) Burnup for Fuel Rod #H8T (calculated)

C-87
I
C-89
#B9T initial IndwglI Ml ctmaici of Refabricated Fuel Rods :c'!

.(g3 ;cpamtc addg) ,d:iS I

Table C-9.1. Axial Distribution of Isotopic Composition for Fuel Rod 01B9T (calculated)

Axial coordinate Nuclear concentrations

from lower end (kg/t U)

of fuel rod

(mm) U235 . U23' I U238 I PU29 I PU240 PU24

1 pu242

20

25

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

165

170

175

180

4.50

4.50

4.58

4.63

4.47

4.32

4.37

4.40

4.42

4.45

4.66

4.84

4.79

4.73

4.71

4.68

4.58

4.45

4.50

4.55

4.60

4.63

4.63

4.63

4.76

4.90

4.76

4.60

4.73

4.73

4.73

4.95

4.95

4.95

4.94

4.95

4.97

4.96

4.96

4.96

4.96

4.94

4.92

4.93

4.93

4.93

4.94

4.95

4.96

4.95

4.95

4.94

4.94

4.94

* 4.94

4.93

4.92

4.93

4.94

* 4.93

4.93

4.93

927

927

927

927

927

926

926

926

926

926

927

928

928

927

927

927

927

926

927

927

927

927

927

927

928

928

928

927

927

927

927

4.88

4.88

4.90

4.91

4.87

4.84

4.85

4.86

4.86

4.87

4.91

4.94

4.93

4.93

4.92

4.92

4.90

4.87

4.88

4.89

4.90

4.91

.4.91

4.91

4.93

4.95

4.93

4.90

4.93

4.93

4.93

2.66

2.66

2.65

2.64

2.66

2.68

2.68

2.67

2.67

2.67

2.64

2.62

2.63

2.63

2.63

2.64

2.65

2.67

2.66

2.65

2.65

2.64

2.64

2.64

2.63

2.62

2.63

2.65

2.63

2.63

2.63

1.589

1.589

1.588

1.588

1.589

1.588

1.588

1.589

1.589

1.589

1.588

1.583

1.585

1.587

1.588

1.588

1.588

1.589

1.589

1.589

1.588

1.588

1.588

1.588

1.586

1.581

1.586

1.588

1.587

1.587

1.587

1.076

1.076

1.063

1.055

1.080

1.107

1.098

1.094

1.089

1.085

1.050

1.020

1.029

1.037

1.042

1.046

1.063

1.085

1.076

1.068

1.059

1.055

1.055

1.055

1.033

1.011

1.033

1.059

1.037

1.037

1.037

All numerical values orcharacteristics presented as average values at the length interval equal to the axial coordinate I 2.5 mm

C-90
#B9T I ,::±. cadin) +

Table C-9.2. Radial Distribution of Burnup (Calculated) and Isotopic Composition with RIM Zone

Indication (Calculated) for Fuel Rod #B9T (average values In fuel rod)

Coordinates of fuel radial zones (mm)

Characteristic I zone 2 zone 3 zone 4 zone

1.2 - 2.811 2.811 - 3.A32 3.432 - 3.704 3.704 - 3.790

1. Nuclear concentrations

(kg/t U):

u235 4.75 4.55 4.36 4.24

u236 4.95 4.94 4.94 4.95

U238 933. 929. 917. 884.

Pu239 4.12 4.58 6.16 10.42

Pu240 2.35 2.46 3.13 5.06

pU241 1.275 IA80 2.082 3.708

Pu242 0.827 0.986 1.428 2.631

2. Burnup 45.4 48.3 56.7 79.6

(MWd/kg U)

C-91
#B9T I',n'i ia~ris of Rcfabricated Fuel Rod i

I (Peir ffbdfl~iXUXId cla~ddinlg) ; fi-4 II

Table C-93. Individual Initial Characteristics for Fuel Rod #B9T (measured)

Axial coordi- Cladding Cladding Fuel mass (g) Linear Free gas Bumup

nate from outer outer (density- fuel volume (MWdlkg U)*

lower end diameter diameter 10.134) g/cm3)* mass (mm3)'5)

of fuel rod at 00 at 90° (glcm)*

(mm) (mm) (mm) _

5

10

15

20')

25

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

165

1702)

175

180

9.097

9.086

9.081

9.091

9.103

9.098

9.091

9.088

9.091

9.092

9.080

9.069

9.068

9.072

9.083

9.086

9.083

9.080

9.091

9.095

9.098

9.081

9.072

9.075

9.078

9.080

9.075

9.071

9.075

9.091

9.097

9.100

9.091

9.088

9.089

9.089

9.083

9.080

9.081

9.089

9.091

9.086

9.081

9.077

9.086

9.081

9.077

9.066

9.071

9.086

9.088

9.075

9.074

9.080

9.084

9.084

0.0

0.0

0.0

1.02

2.07

2.07

2.05

2.05

2.05

2.03

2.02

2.02

2.00

1.99

1.99

1.99

1.99

1.99

2.00

2.02

2.04

2.05

2.07

2.08

2.10

2.11

2.08

2.07

2.06

2.05

2.12

1.43

0.85

0.42

0.0

0.0

0.0

0.0

0.0

4.08

4.14

4.15

4.09

4.10

4.09

4.05

4.04

4.03

4.01

3.99

3.97

3.97

3.98

3.99

4.00

4.03

4.07

4.10

4.13

4.16

4.20

4.21

4.16

4.13

4.13

4.09

4.24

2.86

1.69

1.70

0.0

0.0

8.8

98.9

234.0

133.6

30.3

30.3

32.3

32.3

32.3

34.2

35.2

35.2

37.2

38.2

38.2

38.2

38.2

38.2

37.2

35.2

33.3

32.3

30.3

29.3

27.3

26.4

29.3

30.3

31.3

32.3

25.4

.93.3

150.4

192.7

234.0

136.0

0.0

- 0.0

50.2

50.2

49.9

49.6

50.3

50.9

50.7

50.5

50.5

50.4

49.6

48.9

49.1

49.3

49.4

49.5

49.9

50.3

50.1

50.0

49.8

49.7

49.7

49.7

49.2

- 48.6

49.2

49.8

49.33)

49.33)

49.33)

0.0

0.0

' These numerical values of characteristics arm presented as average values at the length interval equal to the axial coordinate ± 2.5 mm

I) Initial coordinate of fuel is 20.0 mm 4) Effective density of fuel stack

2) Final coordinate of fuel is 170 mm

3) Average value

Free gas volume for coordinates I 5 - 295 mm

is presented in Table C.3

C-92
#B9T I a ChatCistics uof Rifabrntei FuelRo*.;

Triate rdcladcddig) =.-- V I

nn11n(111 .

10000-

'n

1.

:4

._

(#1

8000-

6000-

Cs 137 *........ CS1"4

_ 'Ru 0 l'

:..r^ .,: I . r;..s : ...: 

L.;.

t .

4000-

2000-

I I

0

I 1

50

I A

100

a)

I I I a &

150 200

Axial coordinate (mm)

250

b)

5.0

4.0

E

2he

I@;

r-

.- I

3.0

2.0

S

E

CD0

Ca

1.0

0

0 50 100 150 200 250

c) Axial coordinate (mm)

Fig. C-9.1. (a) Results of y-scanning, (b) Radiography, (c) Axial Fuel Mass Distribution and Axial Free

Gas Volume Distribution for Fuel Rod #B9T

C-93
#B9T Tnidlaftn l Indf3ics of Refa rcated Fuelisps '

clDasdduins)- -v

60

50

40

30

I I

50 100 150 200 250

a) Axial coordinate (mm)

9.4

4)

1._

E

9

0

l..

0

to

0-

9.3

9.2

9.1

9.0

b) Axial coordinate (mm)

150 250

C) Axial coordinate (mm)

Fig. C-9.2. (a) Axial Burnup Distribution and (b) Results of Profilometry and (c) Eddy-Current

Examination for Fuel Rod MB9T

C-94
#B9T I iictristiaso~fbicA Oid - id F-,1.' 11.il

10

CE

CF)

.0

C.

O

8

6

4

u238

-a== okX239 "U"

0 40 80 120 160

a) Axial coordinate (mm)

1000

800 6

O4 0

600 c

0

r.

400 * o

200

0

2

0

1.2

0

0

C)

0

0

C S

~Cq

U23 s

I

0.8 -

0.6-

*II

3.

<1

Si.

I11

It

Iv

0.4 -

0.2-4- ._._____________ . ' _

1 2 3 4

b) Radial fuel coordinate (mm)

Fig. C-93. (a) Axial Distribution of U351, Um8, Pu239, Pay4 Isotopes and (b) Radial Distribution

of U25 Isotope for Fuel Rod #B9T (calculated)

C-95
#B9T [,Piv -iiiLY,,rvij~dll 10csfkifabrkictid Fellti,

~ cladding) ;2' e,' 'I

E

0

~a

1.2

1.0

pu 23

0.8

0.611 _____ 1__-_

IV

0.4 -

0.2 -

] - h

I f'2i!

E .. .,?C._, .; .

''r."'.'.'<

v f .:, i

.m-

,,^S, A, . .

S ?_l . ;. ..

?I, ,>* : ,,.>~', A.,..

2

I I a

1 3

Radial fuel coordinate (mm)

4

PE-.

U-5

0

a)

0

a 't C

- Zs

la )

z '45

1.2

1.0

0.8

0.6

Pu24'

0.4 1- I -

,

q .. .

, i,..,i.

.:''.t

. o t +;

w-H1

> ....

e w

. i - 'L i "..

a S_ ._ t_

. S .,'',.

I

1

2

... I - :

t. ,'. , :

0.2

I .3

Radial fuel coordinate (mm)

Fig. C-9.4. Radial Distribution of Pu239, Pu241 Isotopes for Fuel Rod #B9T (calculated)

C-96
#B9T Iii atetisdcsfRefabncaed Fuei Rods:.-> I

1 mesdid~~irradiated claddixig) -,' i"nrui w

-1.2

Fs

.0

1.0

9 0.8

C) 0

c 0.6

.)

C)

'0- 0.4

t, *-

-.2 - Q

ZV2

I I I . I I

1 2 3 4

a) Radial fuel coordinate (mm)

1.2

,gL 1.0

E

* 0.8

CL

m2E 0.4

*1

-4 + 3s

+ +

-4 4

--1 II

Ill

IV

0.2-1- .

I 2 3 4

b) Radial fuel coordinate (mm)

Fig. C-9.5. (a) Radial Distribution of U238 Isotope and (b) Burnup for Fuel Rod #B9T (calculated)

C-97

c-99
A#B1OT I lm aiicsw of Refabnc>td Fuel R cds K.

I (P aiTnm 3Miii addbi' ). t- i 3d am A

Table C-10.1. Axial Distribution of Isotopic Composition for Fuel Rod #B1OT (calculated)

Axial coordinate Nuclear concentrations

from lower end (kg/t U)

of fuel rod

(mm) U2

35 I U236 I U238 I pu239 I pu240 I Pu241 I pu242

20

25

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

165

170

175

180

7.07

7.07

7.07

7.01

7.10

7.20

7.53

7.87

7.63

7.43

7.47

7.50

7.33

7.20

7.10

7.01

7.04

7.07

7.10

7.10

7.04

7.01

6.94

6.88

6.79

6.79

6.79

6.79

6.79

6.79

6.79

4.74

4.74

4.74

4.75

4.74

4.73

4.69

4.65

4.68

4.70

4.70

4.70

4.71

4.73

4.74

4.75

4.75

4.74

4.74

4.74

4.75

4.75

4.76

4.77

4.78

4.78

4.78

4.78

4.78

4.78

4.78

931

931

931

931

931

931

932

933

933

932

932

932

932

931

931

931

931

931

931

931

931

931

931

931

930

930

930

930

930

930

930

5.73

5.73

5.73

5.73

5.74

5.75

5.78

5.80

5.79

5.77

5.77

5.77

5.76

5.75

5.74

5.73

5.73

5.73

5.74

5.74

5.73

5.73

5.72

5.72

5.71

5.71

5.71

5.71

5.71

5.71

5.71

2.50

2.50

2.50

2.51

2.50

2.48

2.44

2.39

2.43

2.45

2.45

2.44

2.47

2.48

2.50

2.51

2.50

2.50

2.50

2.50

2.50

2.51

2.52

2.53

2.54

2.54

- 2.54

2.54

2.54

2.54

2.54

1.673

1.673

1.673

1.677

1.671

1.666

1.647

1.623

1.640

1.652

1.650

1.649

1.658

1.666

1.671

1.677

1.675

1.673

1.671

1.671

1.675

1.677

1.680

1.684

1.689

1.689

1.689

1.689

1.689

1.689

1.689

0.785

0.785

0.785

0.793

0.781

0.770

0.732

0.697

0.721

0.744

0.740

0.736

0.755

0.770

0.781

0.793

0.789

0.785

0.781

0.781

0.789

0.793

0.800

0.808

0.820

0.820

0.820

0.820

0.820

0.820

0.820

All numerical values of characteristics presented as average values at the length interval equal to the axial coordinate * 2.5 mm

C-100
#B1OT Initial Ind Characteristics of Refabricated Fuel Rods , |

| dPue iPreirradiated e cladding) -:-: .. - |

Table C-10.2. Radial Distribution or Burnup (Calculated) and Isotopic Composition with RIM Zone

Indication (Calculated) for Fuel Rod #B1OT (average values in fuel rod)

Coordinates of fuel radial zones (mm)

Characteristic I zone 2 zone 3 zone 4 zone

1.2 - 2.811 2.811 - 3.432 3.432 - 3.704 3.704 - 3.790

1. Nuclear concentrations

(kg/t U):

u235 7.25 7.00 6.77 6.62

u236 4.74 4.75 4.76 4.77

U23' 937. 933. 922. 892.

Pu239 4.80 5.35 7.24 12.41

Pu240 2.19 2.32 3.00 4.94

pu24

1 1.329 1.557 2.213 3.994

Pu242 0.609 0.731 1.065 1.971

2. Burnup 39.5 41.9 48.9 67.7

(MWd/kg U)

C-101
#B1OT Initial Individual-ic=tcristics ofRefabricated Fuel Rods:

(Preirmadiated fie diated cladding) . -.

Table C-10.3. Individual Initial Characteristics for Fuel Rod #BIOT (measured)

Axial coordi- Cladding Cladding Fuel mass (g) Linear Free gas Burnup

nate from outer outer (density- fuel volume (MWd/kg U)*

. lower end diameter diameter 10.134) g/cm3 )* mass (mm3)"5

of fuel rod at 00 at 90° (gtcm)*

(mm) (mm) (mm)

5

10

15

20

25')

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

165

170

1752)

180

9.068

9.077

9.081

9.072

9.068

9.078

9.086

9.084

9.068

9.059

9.065

9.080

9.080

9.074

9.066

9.074

9.084

9.086

9.086

9.084

9.095

9.113

9.110

9.109

9.103

9.097

9.095

9.094

9.097

9.084

9.084

9.089

9.097

9.095

9.083

9.091

9.100

9.110

9.104

9.092

9.088

9.092

9.098

9.094

9.094

9.092

9.092

9.092

9.083

9.068

9.068

9.081

9.092

9.092

9.097

9.097

0.0

0.0

0.0

0.0

0.96

1.60

1.75

1.99

2.06

2.15

2.16

2.17

2.18

2.17

2.15

2.13

2.11

2.07

2.06

2.03

2.01

2.01

2.01

2.00

2.00

2.01

2.01

1.98

1.88

*1.68

0.96

0.94

1.09

1.35

0.20

0.0

0.0

0.0

0.0

:.0.

3.84

3.20

3.50

3.97

4.11

4.30

4.32

4.34

4.36

4.35

4.31

4.27

4.21

4.15

4.11

4.06

4.03

4.02

4.01

3.99

4.01

4.02

4.02

3.96

3.76

3.36

1.92

1.88

2.18

2.69

3.90

0.0

8.8

98.9

234.0

234.0

139.5

76.6

61.8

38.2

31.3

22.4

21.4

20.5

19.5

20.5

22.4

24.4

26.4

30.3

31.3

34.2

36.2

36.2

36.2

37.2

37.2

36.2

36.2

39.2

49.0

68.7

139.6

141.5

126.8

101.2

214.3

114.8

0.0

0.0

0.0

43.130

43. O

43.1 3

43.4

43.1

42.7

41.7

40.7

41.4

42.0

41.9

41.9

42.3

42.7

43.0

43.4

43.2

43.1

43.1

43.1

43.2

43.4

43.6

43.8

44.13)

44.13)

44.13)

44.13)

44.13)

44.1 3

44.13)

0.0

* These numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate * 2.5 mm

I) Initial coordinate offuet is 25.0mm 4) Eflective density of fuel stack

2) Final coordinate of fuel is 173 mm

3) Average value

5) Free gas volume for coordinates 185 - 295 mm

is presented in Table C.3

C-102
#BIOT Initial nd,'4rCharacteristics of Refabricated Fuel Rods -

I (PreinadL Preirradiated cladding) - . ; - K |

,a

C:

.2n

0 50 100 150 200

a) Axial coordinate (mm)

250

b)

5.0

4.0

3.0

2.0

1.0

0

E5

E

0

0

0 50 100 150 200 250

c) Axial coordinate (mm)

Fig. C-10.1. (a) Results oty-scanning, (b) Radiography, (c) Axial Fuel Mass Distribution and Axial

Free Gas Volume Distribution for Fuel Rod B1OT

C-103
#B1OT |initial ndiviMdual rjistics of Refabricated Fuei Rods

(PreiradiatedfiQ f z iated cladding) - -

0. 2:

E

50 -

40-~~ 1<1

0 50 100 150 200 250

a) Axial coordinate (mm)

9.4

I0

._

a.=

to

. E

CA

0

2

9.3

9.2

9.1

9.0

0 50 100 150

b)

200 250

Axial coordinate (mm)

50

c) Axial coordinate (mm)

Fig. C-10.2. (a) Axial Burnup Distribution and (b) Results of Profllometry and (c) Eddy-Current

Examination for Fuel Rod #BIOT

C-104
MBOT Initial Indiv"W"hItharacteristics of Refabricated Fuel Rods i I

I (Preinrd l Preirradiatedcladding) . :-. ,

10

p

-

0_

CL

C)

0

U

C

z

8

6

4

2

0

1.2

E

9 1.0

1i2 C)

+j 0.8

E

C)

0

Ct 0.6

C

0

.z

0 0.4

U

I- ._:

ev =

= Qv 0.2

Z' la

_ ' u235_

_..... . . . . . .. . ... . .. .. . ........ . ....................... ; .........

. . 'PU239

.....- .-....-..-.... ..........

_Pu_

Pu2 41

0 40 80 120 160

a) Axial coordinatc (mm)

u 235

.777I

*IV

_ _ .A

1000

800 S

0

600

400 o

L.v

200

0

I 4

Radial fuel coordinate (mm)

-1

b)

Fig. C-10.3. (a) Axial Distribution of 5 5 ,U 238, Pu3 9, Pu241 Isotopes and (b) Radial Distribution

of Ue' Isotope for Fuel Rod #BIOT (calculated)

C-105
#B1OT Initial ndiaiduaf6li'%dstics of Refabricated Fuel Rods - . .I

(Preirradiatedfu idiatedcladding), i- ; _ : |

E

In

0

U

0

0

S.. -

- S

23

2

U

23

23

U'-a

0

23

0

23

U

U

23

0

o

-

1.2

1.0

0.8

0.6

0.4

0.2

1.2

1.0

0.8

0.6

-Y

Pu 2 39

-4 l. l 5

'a,IV

II

1* I I

.III

A

1 2 3 4

Radial fuel coordinate (mm)

UIV

I

0.4 -*1 -

0.2 -

-........

:vs .

' :- .--,

: 111,: '-'. ''''.

....

., .

.1

II -, . 'K a

_ . . . . _ _

T T I

2

I I i

I 4

Radial fuel coordinate (mm)

Fig. C-10.4. Radial Distribution of Pu239, Pu241 Isotopes for Fuel Rod #BlOT (calculated)

C-106
#B1OT lai Li 0A I n10' U hiii haracteristics of Refabricated Fuel Rods" I (Preirradilwfuoe ,Preirradiated cladding).' _~- !_:' I." 

1.2-

E

E- 1.0-

5

g 0.8-

0

00.6-

o 0.4-

2 -..

Q S

z.s,

Un3

_ -

t1-

_ _

1

I

./ 1

I

:i

II

IV

L

V. / - _ _-. . _ . __

G

1 2

I

3

I

4

a) Radial fuel coordinate (mm)

1.2 -- Y *I.

I-U

0.

E

.E

m2E

1.0

0.8

0.6

4 + **5-

4 +

. ..

0.41- L II

- ,- .

o "' ';

;: -: < . - .

:-..

-:

, .,III,,

: . ti -

; 5 A..... 5

. .

- -:

"V

0.2 -4-

2 3

I

I

b) Radial fuel coordinate (mm)

Fig. C-10.5. (a) Radial Distribution of U28 Isotope and (b) Burnup for Fuel Rod #BlOT (calculated)

C-107

C-109
#B11T Initial Individual hmtristics of Refabricated Fuel Rods - :

| (Preirraidiatedfie~ j;iuiaated cladding) - A ; -

Table C-11.1. Axial Distribution of Isotopic Composition for Fuel Rod #Bl1T (calculated)

Axial coordinate Nuclear concentrations

from lower end (klg/t U)

of fuel rod

(mm) U235 U236 J U238 I pU239 I PU240 I PU24' I PU242

20

25

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

165

170

175

180

7.23

7.23

7.17

7.10

7.07

7.10

7.10

7.17

7.20

6.85

6.79

6.69

6.69

6.85

6.91

6.85

6.82

7.07

7.13

6.85

6.79

6.91

6.91

6.91

6.91

6.91

6.91

6.91

6.91

6.91

6.91

6.91

6.91

4.73

4.73

4.73

4.74

4.74

4.74

4.74

4.73

4.73

4.77

4.78

4.79

4.79

4.77

4.76

4.77

4.77

4.74

4.74

4.77

4.78

4.76

4.76

4.76

4.76

4.76

4.76

4.76

4.76

4.76

4.76

4.76

4.76

932

932

931

931

931

931

931

931

931

930

930

930

930

930

931

930

930

931

931

930

930

931

931

931

931

931

931

931

931

931

931

931

931

5.75

5.75

5.74

5.74

5.73

5.74

5.74

5.74

5.75

5.71

5.71

5.70

5.70

5.71

5.72

5.71

5.71

5.73

5.74

5.71

5.71

5.72

5.72

5.72

5.72

5.72

5.72

5.72

5.72

5.72

5.72

5.72

5.72

2.48

2.48

2.49

2.50

2.50

2.50

2.50

2.49

2.48

2.53

2.54

2.55

2.55

2.53

2.52

2.53

2.53

2.50

2.49

2.53

2.54

2.52

2.52

2.52

2.52

2.52

2.52

2.52

2.52

2.52

2.52

2.52

2.52

1.664

1.664

1.668

1.671

1.673

1.671

1.671

1.668

1.666

1.686

1.689

1.695

1.695

1.686

1.682

1.686

1.688

1.673

1.670

1.686

1.689

1.682

1.682

1.682

1.682

1.682

1.682

1.682

1.682

1.682

1.682

1.682

1.682

0.766

0.766

0.773

0.781

0.785

0.781

0.781

0.773

0.770

0.812

0.820

0.831

0.831

0.812

0.804

0.812

0.816

0.785

0.777

0.812

0.820

0.804

0.804

0.804

0.804

0.804

0.804

0.804

0.804

0.804

*0.804

0.804

0.804

All numerical values of characteristics presented as average values at the length interval equal to the axial coordinate ± 2.5 mm

C-l1
#B11T Initial Indilal haractristics of Refabricated Fuel Rodg

v(reiiradink i Preirradiated cladding) -4, -.-. ! ',,- I .' .-

Table C-11.2. Radial Distribution of Burnup (Calculated) and Isotopic Composition with RIM Zone

Indication (Calculated) for Fuel Rod #B11T (average values in fuel rod)

Coordinates of fuel radial zones (mm).

Characteristic I zone 2 zone 3 zone 4 zone

1.2 - 2.811 2.811 - 3.432 3.432 - 3.704 3.704 - 3.790

1. Nuclear concentrations

(kg/t U):

u235 7.09 6.85 6.62 6.46

u236 4.76 4.77 4.78 4.79

u238 936. 933. 922. 891.

PU239 4.79 5.33 7.22 12.36

Pu240 2.21 2.34 3.02 4.97

pu241 1.336 1.565 2.224 4.010

Pu242 0.624 0.749 1.091 2.019

2. Burnup 39.9 42.4 49.5 68.6

(MWd/kg U)

I

C- 11
#B11T Initial Individual ~th ristics of Refabricated Fuel Rods . -

(Preirradiated fIlae diated cladding) - I

Table C-11.3. Individual Initial Characteristics for Fuel Rod #B11T (measured)

Axial coordi- Cladding Cladding Fuel mass (g) Linear Free gas Burnup

nate from outer outer (density- fuel volume (MWd/kg U)*

lower end diameter diameter 10.134) g/cm3 )* mass (mm3 )*5

of fuel rod at 00 at 900 (g/cm)*

(mm) (mm) (mm)

5

10

15

20')

25

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

165

170

175

1802)

9.106

9.107

9.106

9.103

9.097

9.101

9.104

9.106

9.104

9.104

9.113

9.113

9.095

9.088

9.088

- 9.095

9.097

9.097

9.095

9.097

9.103

9.106

9.112

9.116

9.122

9.112

9.095

9.086

9.104

9.103

9.107

9.109

9.109

9.101

9.094

9.095

9.097

9.092

9.089

9.097

9.109

9.110

9.109

9.109

9.103

9.113

9.113

9.104

9.100

9.091

9.092

9.092

9.098

9.113

9.119

9.128

0.0

0.0

0.0

0.42

1.65

2.00

1.93

2.05

2.07

1.97

2.03

2.04

1.99

1.84

1.99

2.02

2.05

2.06

2.09

2.10

2.10

2.08

2.06

2.00

1.65

1.83

1.96

1.87

1.58

1.74

1.18

1.38

1.56

1.20

1.06

0.21

0.0

0.0

0.0

1.05

3.30

4.00

3.85

4.09

4.15

3.94

4.07

4.07

3.97

3.69

3.98

4.04

4.09

4.13

4.17

4.21

4.20

4.16

4.12

4.00

3.30

3.66

3.93

3.73

3.16

3.48

2.37

2.76

3.11

239

2.12

2.10

8.8

98.9

234.0

192.7

71.6

37.2

44.1

32.3

30.3

40.1

34.2

33.3

38.2

52.9

38.2

35.2

32.3

31.3

28.3

27.3

27.3

29.3

31.3

37.2

71.6

53.9

41.1

50.0

78.5

62.8

117.9

98.2

80.5

115.9

129.7

94.1

0.0

0.0

42.6 3

42.6 3

42.8

43.1

43.1

43.0

43.0

42.8

42.7

43.8

44.1

44.3

44.4

43.8

43.7

43.9

44.0

43.1

42.9

43.9

44.1

43.73)

43.73)

4373)

43.73)

43.73)

43.73)

43.73)

43.73)

43.73)

43.73)

43.73)

43.73)

* * These numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate 2.5 mm

I) Initial coordinate of fuel is 18.5 mm 4) Effective density of fuel stack

2) Final coordinate of fuel is 178.5 mm

3) Average value

5) Free gas volume for coordinates 185 - 295 mm

is presented in Table C.3

C-112
#BIIT Initial IndEli Characteristics of Refabricated Fuel Rods.

O MPrirai irradiatedcladdin0%.'-;: .- --

X

Con

C

0 50 100 150 200 250

a) Axial coordinate (mm)

:Tglmdz

b)

E

2

E

0

in

0 50 100 150 200 250

c) , Axial coordinate (mm)

Fig. C-11.1. (a) Results ofy-scanning, (b) Radiography, (c) Axial Fuel Mass Distribution and Axial

Free Gas Volume Distribution for Fuel Rod #B11T

C-1 13
#BIIT Initial Individuil ha-actistics of Refabricated Fuel Rods. I -

(Preirradiated fuel,5 ?diated cladding),: . - '

60

50

40

30

0 50 100 150 200 250

a) Axial coordinate (mm)

9.4

E

E

I..

.)

0

0

to

rla

._

0

E

C"

9.3

9.2

9.1

9.0

b) Axial coordinate (mm)

1.0

0 50 100 150 200 250

c) Axial coordinate (mm)

Fig. C-11.2. (a) Axial Burnup Distribution and (b) Results of Profilometry and (c) Eddy-Current

Examination for Fuel Rod #B11T

C-114
#B11T Initial mid u i~characteristics of Refabricaied Fuel Rods . |

(Preirrcdli rein-adiatedcladding) -. - --: V ;- |

10

0

Ict,

z

8

6

4

2

0

1.2

... _.p. ,,,,,,, . ............

Pu2 41

.P

0 40. 80 120 160

a) Axial coordinatc (mm)

.

. ;.I .. I

1000

S

800 S

E

0

600 _

8

r400 o

0

CI..

200 Z

0

E

E

.E

0

. W

0

P)

U

0

E

:C

Z

1.0

0.8

0.6

0.4

0.2

2 . 3

Radial fuel coordinate (mm)

4

b)

Fig. C-11.3. (a) Axial Distribution of U235 U238, Pu 239, PuU24 Isotopes and (b) Radial Distribution

of U235 Isotope for Fuel Rod #B11T (calculated)

C-115
#B11T Initial Individuai .Cri stics of Refabricated Fuel Rods ,.- .

(Preinadiated fuel sidiated cladding) - - : -- . : :

E

U

C.)

0

U

U

0

o

on - S

U'-

2

U

4-

U

0

0

U

U

0

C.) '

U n* - I

U'-

nO

ZS?

1.2

1.0

0.8

0.6

0.4

0.2

1.2

1.0

0.8

0.6

0.4

0.2

2 3 4

Radial fuel coordinate (mm)

PeI

1 2 3 4

1 2 3

Radial lfeielcoordinate (mm)

4

Fig. C-11.4. Radial Distribution of Pu239, Pu241 Isotopes for Fuel Rod #1B11T (calculated)

C-116
#B11T initial Ind cteristics of Refabricated Fuel Rods l

d Preirradated cladding) I -. : .-- I

S

.9

U

0

Po

n.n

E

.+d

..- E

8s:

0 =

lu IL

Z P

1.2

1.0

-in

u 2 3 3

)-I-p _

0.8 -

0.6 -

*1

$1

II

0.4 -1-

0.2 _ . . - - .

l

2

l

I 3 4

a) Radial fuil coordinate (mm)

1.2

I-.

Cl

la

S

0.

I A I _ --I '-1 1.s -

0.8 -

0.6 -

t -

0.4 4-

'I

I

5*

:1

II

III

k

'V

0.2 T T I

3

T

1 2 4

b) Radial fuel coordinate (mm)

Fig. C-11.5. (a) Radial Distribution of U238 Isotope and (b) Burnup for Fuel Rod #BllT (calculated)

C-1 17
I
*C-119,
#B12T Initial Individual Ciateristics of Refabricated Fuel Rods 1

(Preirradiated fuXe1relrradiated cladding) - - I

Table C-12.1. Axial Distribution of Isotopic Composition for Fuel Rod #B12T (calculated)

Axial coordinate Nuclear concentrations

from lower end (kg/t U)

of fuel rod

(mm) U235 I U236 u 238 Pu239 . pU240 I pu24

1 I pU242

10

15

20

25

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

165

170

4.94

4.94

4.94

4.94

4.94

4.94

4.94

4.94

4.94

4.94

4.94

4.94

4.94

4.94

4.94

4.94

4.94

4.94

4.94

4.94

4.94

5.21

5.13

5.04

5.18

5.37

5.46

5.46

5.46

5.46

5.46

5.46

5.46

* 4.93

4.93

4.93

4.93

4.93

4.93

4.93

4.93

4.93

4.93

4.93

4.93

4.93

4.93

4.93

4.93

4.93

4.93

4.93

4.93

4.93

4.91

4.92

4.92

4.91

4.89

4.89

* 4.89

4.89

4.89

4.89

4.89

4.89

927

927

927

927

927

927

927

927

927

927

927

927

927

927

927

927

927

927

927

927

927

927

927

927

927

928

928

928

928

928

928

928

928

5.13

5.13

5.13

5.13

5.13

5.13

5.13

5.13

5.13

5.13

5.13

5.13

5.13

5.13

5.13

5.13

5.13

5.13

5.13

5.13

5.13

5.16.

5.15

5.14

5.16

5.19

5.21

5.21

5.21

5.21

5.21 -

5.21

5.21

2.68

2.68

2.68

2.68

2.68

2.68

2.68

2.68

2.68

2.68

2.68

2.68

2.68

2.68

2.68

2.68

2.68

2.68

2.68

2.68

2.68

* 2.65

2.66

2.67

2.65

2.63

2.62

2.62

2.62

2.62

2.62

2.62

2.62

1.657

1.657

1.657

1.657

1.657

1.657

1.657

1.657

1.657

1.657

1.657

1.657

1.657

1.657

1.657

1.657

1.657

1.657

1.657

1.657

1.657

1.648

1.650

1.654

1.649

1.645

1.643

1.643

1.643

1.643

1.643

1.643

1.643

1.043

1.043

1.043

1.043

1.043

1.043

1.043

1.043

1.043

1.043

1.043

1.043

1.043

1.043

1.043

1.043

1.043

1.043

1.043

1.043

1.043

1.001

1.013

1.026

1.005

0.976

0.964

0.964

0.964

0.964

0.964

0.964

0.964

All numerical values of characteristics presented as average values at the length interval equal to the axial coordinate ± 2.5 mm

C-120
I nidal ndtdul Characteristics-of Refabricated Fuel Rods |

#B12T | (PxeiradRluae Preiffadiated cladding) .

Table C-12.2. Radial Distribution of Burnup (Calculated) and Isotopic Composition with RIM Zone

Indication (Calculated) for Fuel Rod NB12T (average values in fuel rod)

Coordinates of fuel radial zones (mm)

Characteristic I zone 2 zone 3 zone 4 zone

1.2 - 2.811 2.811 - 3.432 3.432 - 3.704 3.704 - 3.790

1. Nuclear concentrations

(kg/t U):

U235 5.28 5.07 4.87 4.74

4.92 4.92 4.92 4.92

u238 933. 930. 917. 884.

PU239 4.32 4.81 6.48 10.99

Pu240 2.36 2A7 3.16 5.12

Pu241 1.320 1.536 2.168 3.872

Pu242 0.790 0.944 1.370 2.526

2. Burnup 44.5 47.3 55.6 77.9

(MWd/kg U)

C-121
#B12T Initial Individual CImfferistics of Refabricated Fuel Rods, -. I (Preirradiated fiuel V~iradiated cladding) : : -- : ..- : I: 

Table C-12.3. Individual Initial Characteristics for Fuel Rod #B12T (measured)

Axial coordi- Cladding Cladding Fuel mass (g) Linear Free gas Burnup

nate from outer outer (density- -fuel volume (MWd/kg U)*

lower end diameter diameter 10.13 4) gcm

3)* mass (mm3 )"5

of fuel rod at 00 at 90. (gfcm)*

(mm) (mm) (mm)

5

15

20

25

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

165

1702)

175

180

9.100

9.097

9.098

9.103

9.109

9.103

9.091

9.088

9.097

9.100

9.094

9.095

9.104

9.107

9.104

9.091

9.089

* 9.095

9.101

9.100

9.091

9.088

9.097

9.107

9.112

9.107

9.101

9.103

9.091

9.094

9.094

9.080

9.075

9.078

9.086

9.081

9.072

9.074

9.089

9.098

9.097

9.086

9.086

9.092

9.094

9.088

9.086

9.092

9.100

9.107

9.097

9.080

9.074

9.078

9.083

9.081

0.0

0.07

0.18

0.70

1.49

1.50

1.52

1.41

1.25

1.51

1.89

1.66

1.31

1.38

1.48

1.67

1.96

1.79

1.53

1.45

1.33

1.60

1.99

2.03

2.04

2.07

2.08

1.76

1.25

1.24

1.23

1.29

1.38

0.84

0.0

0.0

0.0

0.34

0.35

1.41

2.99

3.01

3.03

2.82

2.50

3.02

3.79

3.32

2.62

2.75

2.95

3.34

3.91

3.57

3.06

2.90

2.65

3.21

3.99

4.05

4.09

4.14

4.15

3.53

2.51

2.49

2.46

2.58

2.76

2.76

0.0

0.0

8.8

92.0

216.3

165.1

87.4

86.4

84.4

95.3

111.0

85.4

48.0

70.7

105.1

98.2

88.4

69.7

41.1

57.9

83.4

91.3

103.1

76.6

38.2

34.2

33.3

30.3

29.3

60.8

111.0

112.0

113.0

107.1

98.2

151.4

234.0

114.8

49.53)

49.53)

49.53)

49.53)

49.53)

49.53)

49.53)

49.53)

49.53)

49.53)

49.53)

49.53)

49.53)

49.53)

49.53)

49.53)

49.53)

49.53)

49.53)

49.53)

49.53)

48.5

48.7

49.1

48.6

47.9

47.53)

47.53)

47.53)

47.53)

47.53)

47.53)

47.53)

0.0

0.0

\

L I I .1. A. A.

* These numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate * 2.5 mm

)Initial coordinate of fuel is 10.5 mm ) Effective density of fuel stack

2) Final coordinate of fuel is 172.5 mm

3) Average value

5) Free gas volume for coordinates 185 - 295 mm

is presented in Table C3

C-122
#B12T Initial IndiviadtuiCharacteristiks of Refabricated Fuel Rods -.- -

(PreirradiM l. Preirradiated cladding) -; -(. |

'Iquuu I

20000-

-In C}

.4

c~

16000-

12000-

Cs'3 7

;...-.;.......Cs '

Rul"r

:..... 800C

400C

0

5.0

4.0

I0 so 100 150 200 25C

a) Axial coordinate (mm)

_11 I

-

b)

v:

iq

v

E;

r1

.-I

3.0

2.0

S

E

C;

al

In0

0

1.0

0

0 50 100 150 200 250

c) - Axial coordinate (mm)

Fig. C-12.1. (a) Results of y-scanning, (b) Radiography, (c) Axial Fuel Mass Distribution and Axial

Free Gas Volume Distribution for Fuel Rod #BI2T

C-123
#B12T Initial Individual d ct6ristics of Refabrcated Fuel Rods -

(Preirridiated fiUe4--_Mjadiated cladding) -- :-

E

Ei

U

.-

U

0

S:

to

r-

.F

0

E

IL

Ae

50-

40- - . _

30-

0 50 100 150 200 25

a) Axial coordinate (mm)

9.3 - 0 =

9.2- | ~~..........--- ......... g° 90

9.1 .

0 50 100 150 200 25

b) Axial coordinate (mm)

.5

.....-- 2mode 2 mode | 

_l0.5

-]

0 50 100 150 200 250

c) Axial coordinate (mm)

Fig. C-12.2. (a) Axial Burnup Distribution and (b) Results of Profilometry and (c) Eddy-Current

Examination for Fuel Rod #B12T

C-124
#B12T I.Iniial Tnd1 [Characteristics of Refabricated Fuel Rods ,

| (fdi Preirradiated cladding) :, -: . - . |

10 *1* *1* T I.. 1000

0

0

%:LS

01

U)

z.

I u 2 3 8

8 .4 4 + 4

6

4

2

0

1.2

. Pu23'

PU241

0 40 80 120 160

a) Axial coordinate (mm)

_ t;. - S - . ' _ a* , . , . [ , 1 ., _ .

.,.-+: ..-- ;,-:.- '!.. -. :----.

_ N ; e, r, ~~, . *> _e ,

S

800 *)

0

600

400 o

0

' I-:

U

200

0

._.

cd

4-

0

.2

0

c

LI

Q

o a. e Z,

Z is

1.0

0.8

0.6

0.4

0.2 I

2

I I

3

Radial fuel coordinate (mm)

4

b)

Fig. C-123. (a)( Axial Distribution of U235, U23', Pu239 , Pu2 4 1 Isotopes and (b) Radial Distribution

of U235 Isotope for Fuel Rod NB12T (calculated)

C-125
I #B12T I nitial Individual Clreteistics of Refabricated Fuel Rods .

| (Preirradiated fe Wdiated cladding) - : I ;. : .. : . -:

i

'.3

C.)

4-.

U

0

0

0

o

- S

z.s,

3,'.3

U

4-.

U

0

0

0

U -

- a o -

no

1.2

1.0

0.8

0.6

0.4

0.2

1.2

1.0

0.8

0.6

0.4

0.2

Pu 2 39

TV

- 4 I . .A

. '-. .

.: . .:. .

. ...

, v .-. ;: - ......

-l11... .....

. -.. . .

. . .: :.- . - -

-I , ... ' ,_ 1 2 3

Radial fuel coordinate (mm)

Pu2'l

i'Li-0 10111

- 777~~, " 1 -4

I

2 3 4

Radial fuel coordinate (mm)

Fig. C-12.4. Radial Distribution of Pu239, Pu24 ' Isotopes for Fuel Rod NB12T (calculated)

C-126
#B12T Initial Tnd iyidaCharacteristics of Refabricated Fuel Rods .

(Prirradik ue7L Preirradiaied cladding) . ..

9.)

0

0

0

U '1

I.-

Un

US1.2

1.0

UM3

_ :

.L For

0.8-i0.6 -

4.

.1<

4, 1

II * III

IV

L

0.4 --

0.2 -l- __ _ ____ _ _ _ _ _ 

I 2 3

I

4

a) Radial fuiel coordinate (mm)

1.2

E-.

SL

#Ila

E0.

23

1.0

0.8

0.6

.4- 4

.4-

0.4 -1- I

-; . ' ' -

,- - - . :.

i.., 11. ,'.,,

', '-', ''. ';. .. ...

. - . ;

III

IV

0.2 -I-.. l

I 2 3 4

b) Radial fuel coordinate (mm)

Fig. C-12.5. (a) Radial Distribution of U238 Isotope and (b) Burnup for Fuel Rod #B12T (calculated)

C-127

- - - J = : -

C-129
4B13T inial fInd ividualt C stics 'of Refabricaied Fuel Rods .

(Preirradiated fieladiated cladding)' -::. I:

Table C-13.1. Axial Distribution of Isotopic Composition for Fuel Rod #1B13T (calculated)

Axial coordinate Nuclear concentrations

from lower end (kg/t U)

of fuel rod

(mm) U23 5 I U 2

36 I U2 3 8 ] pU2 3 9 I pU2 4 0 J Pu 2 4 1 J pu 2 4 2

20

25

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

165

170

175

180

7.18

7.29

7.29

7.25

7.25

7.11

7.11

7.11

7.11

7.08

7.08

7.39

7.39

7.22

7.22

7.50

7.50

7.43

7.43

7.29

7.29

7.32

7.32

7.50

7.50

7.57

7.57

7.75

7.86

7.86

7.86

7.86

4.69

4.68

4.68

4.68

4.68

4.70

4.70

4.70

4.70

4.70

4.70

4.67

4.67

4.69

4.69

4.66

4.66

4.66

4.66

4.68

4.68

4.68

4.68

4.66

4.66

4.65

4.65

4.63

4.61

4.61

4.61

4.61

933

934

934

934

934

933

933

933

933

933

933

934

934

934

934

934

934

934

934

934

934

934

934

934

934

934

934

935

935

935

935

935

5.43

5.44

5.44

5.43

5.43

5.42

5.42

5.42

5.42

5.42

5.42

5.44

5.44

5.43

5.43

5.45

5.45

5.45

5.45

5.44

5.44

5.44

5.44

5.45

5.45

5A6

5.46

5.47

5.48

5.48

5.48

5.48

2.37

2.35

2.35

2.36

2.36

2.38

2.38

2.38

2.38

2.38

2.38

2.34

2.34

2.36

2.36

2.33

2.33

2.34

2.34

2.35

2.35

2.35

2.35

2.33

2.33

2.32

2.32

2.30

2.28

2.28

2.28

2.28

1.542

1.535

1.535

1.537

1.537

1.545

1.545

1.545

1.545

1.547

1.547

1.528

1.528

1.540

1.540

1.522

1.522

1.526

1.526

1.535

1.535

1.533

1.533

1.522

1.522

1.517

1.517

1.506

1.500

1.500

1.500

1.500

0.724

0.713

0.713

0.716

0.716

0.731

0.731

0.731

0.731

0.735

0.735

0.702

0.702

0.720

0.720

0.691

0.691

0.698

0.698

0.713

0.713

0.709

0.709

0.691

0.691

0.684

0.684

0.666

0.655

0.655

0.655

0.655

.1. £ .5. 1 5 1 1

All numerical values of characteristics presented as average values at the length interval equal to the axial coordinate ± 2.5 mm

C-130
#BUT Initial 1ndivi&Characteristics of Refabricated Fuel Rods -.

| (Preirradiafi_ L Preirradiated cladding) . ' -5.. " '-. I I

Table C-13.2. Radial Distribution of Burnup (Calculated) and Isotopic Composition with RIM Zone

Indication (Calculated) for Fuel Rod #B13T (average values in fuel rod)-

Coordinates of fuel radial zones (mm)

Characteristic 1 zone 2 zone 3 zone 4 zone

1.2 - 2.811 2.811 - 3.432 3.432 - 3.704 3.704 - 3.790

1. Nuclear concentrations

(kg/t U):

u235 7.51 7.26 7.02 6.86

u236 4.67 4.68 4.70 4.71

939. 936. 926. 898.

Pu239 4.54 5.07 6.87 11.83

Pu240 2.04 2.18 2.84 4.72

Pu241 1.217 1.424 2.027 3.676

Pu242 0.550 0.659 0.961 1.787

2. Burnup 37.7 40.0 46.4 63.6

(MWd/kg U)

C-131
#B13T Initial Individual Ch*=6cistics of Refabricated Fuel Rods

(Preirradiated fiel, rriraadiated cladding) - .-

Table C-13.3. Individual Initial Characteristics for Fuel Rod #B13T (measured)

Axial coordi- Cladding Cladding Fuel mass (g) Linear fuel Free gas Burnup

nate from outer outer (density- mass volume (MWdlkg U)*

lower end diameter diameter 10.13') g/cm3)* (g/cm)* (mm3 )"5

of fuel rod at 00 at 900

(mm) (mm) (mm)

.5

10

15

201)

25

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

165

170

1752)

180

9.115

9.106

9.106

9.113

9.104

9.091

9.086

9.094

9.100

9.101

9.094

9.091

9.100

9.104

9.104

9.092

9.080

9.084

9.088

9.097

9.095

9.089

9.094

9.107

9.100

9.086

9.078

9.083

9.091

9.088

9.084

9.084

9.095

9.092

9.094

9.088

9.084

9.084

9.089

9.089

9.084

9.077

9.086

9.097

9.106

9.100

9.097

9.094

9.097

9.112

9.115

9.104

9.100

9.109

9.112

9.110

0.0

0.0

0.0

1.18

1.98

2.01

2.03

2.14

2.20

2.07

1.98

1.99

1.99

1.94

1.92

1.99

2.00

2.03

2.05

2.07

2.08

2.09

2.09

2.08

2.06

2.05

2.05

2.04

2.04

2.06

2.04

1.55

1.20

0.58

0.09

0.0

0.0

0.0

0.0

3.95

3.96

4.02

4.05

4.27

4.40

4.13

3.96

3.98

3.98

3.87

3.84

3.98

4.00

4.06

4.10

4.14

4.17

4.17

4.17

4.15

4.12

4.1o

4.09

4.08

4.09

4.12

4.09

3.09

2.41

1.15

0.30

0.0

8.8

98.9

234.0

117.9

39.2

36.2

34.2

23.4

17.5

30.3

39.2

38.2

38.2

43.1

45.1

38.2

37.2

34.2

32.3

30.3

29.3

28.3

28.3

29.3

31.3

32.3

32.3

33.3

33.3

31.3

33.3

81.5

115.9

177.0

131.6

234.0

0.0

0.0

41.5

41.2

41.2

41.3

41.3

41.7

41.7

41.7

41.7

41.8

41.8

40.9

40.9

41.4

41.4

40.6

40.6

40.8

40.8

41.2

41.2

41.1

41.1

40.6

40.6

40.4

40.4

39.9

39.6 3

39.6 3

39.6 3

39.60

0.0

* These numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate i 2.5 mm

1) Initial coordinate of fuel is 19.5 mm 4) Effective density of fuel stack

2) Final coordinate of fuel is 175.5 mm

3) Average value

5) Free gas volume for coordinates 185 - 295 mm

is presented in Table C.3

C-132
#B13T initial Individ~ual Characteristics of Refabricated Fuel Rods; -'

1(PreirradiatMl Preirradiated cladding);.,,, : ' :: . I - --.

2400 I,\ _

1i I .

200001

C.?

16000-

12000-

................ --Cs'"

Ru'06

.. ell . ... .. ; .; .. ........ . .... %--.........

I Ln... 8000-

4 -

4000-

ID I I

0 50 100

a)

I - S

150 200

I

250

Axial coordinate (mm)

I ' C _ R

b)

5.0

4.0

-100

t

E

0

rq

...

3.0

2.0 C's

0

1.0

0

0 50 100 150 200 250

c) Axial coordinate (mm)

Fig. C-13.1. (a) Results of y-scanning, (b) Radiography, (c) Axial Fuel Mass Distribution and Axial

Free Gas Volume Distribution for Fuel Rod #B13T

C-133
Initial Individual thraeristics of Refabricated Fuel Rods'' #B13T (Preirradiated fuad mdiated cladding) - I

E

60

50

40 -r

050 100 150 . 200 25

30

9.4 ,

,-. 9.3, IXa 9.2-

0

O 9.1

9.0

0

a) Axial coordinate (mm)

b) Axial coordinate (mm)

1.0

._-

2 0.5

-

Eb 0.0 -.

Co0

e)

a -0.5

-1.0

0 50 100 150 200 250

c) Axial coordinate (mm)

Fig. C-13.2. (a) Axial Burnup Distribution and (b) Results of Profilometry and (c) Eddy-Current

Examination for Fuel Rod NB13T

C-134
#B13T Initali Indi!Th 4i.,haracteristics of Refabricated Fuel Rods - '

(Preirrd e Preirradiated cladding) -I.: I ' -: .I

10

(44

0

0

C.)

0

UV

z

8

6

4

2

0

1~. -. "l UW

Pu2 4

. . . . . . . . . . . . .r8 .. .. ........ .- .-

0 40 80 120 160

a) Axial coordinate (mm)

u235

_I _I II

', , ; , ; ' I~',, ;-'--

1000

800 -b

0

600 c

f8

400 o

U

i.

C.s

C.)

200 Z

0

1.2

d

C's

0

C

r-

*n C. zi ,

1.0

0.8

0.6

0.4

0.2

I 2 3

Radial fuel coordinate (mm)

4

b)

Fig. C-13.3. (a) Axial Distribution of U235, U238 , Pu239

, Pu241 Isotopes and (b) Radial Distribution

of U235 Isotope for Fuel Rod #B13T (calculated)

C-135 .
#B13T I -nitial Individuald damtristics of Refabricated Fuel Rods'-'|

| (Preirradiatedfii idiated cladding)'. .: -;;

2

cd

C)

.4-.

C)

0

0

8

0

U

o '-

i

2

2

C)

U

0

0

C)

U

0

U -.

-

1.2

1.0

0.8

0.6

0.4

0.2

1.2

1.0

0.8

0.6

0.4

0.2

Pu2

39

IV

2 3 4

Radial fuel coordinate (mm)

Pu_ '

. . I :-, .,~', ''I,>.

I 2 3 4

- Radial fuel coordinate (mm)

Fig. C-13.4. Radial Distribution of Pu 9, Pu241 Isotopes for Fuel Rod #B13T (calculated)

C-136
#B13T Initiil md tharacteristics of Refabricated Fuel RoIds

I (Pmeirrdiatfiu'eL Preirradialed cladding) i. -

C-S

._

vE

U

0

0

El

o

.r-

.2

CX

C) b

,x C)

ZS.F

1.2 -

1.0 -

0.8 -

0.6 -

U 233

I-. - 'U ____ + ;: * . -:; . ............ , . . ., . -. ; - .. ,- .:

,., ;.. -. , . .. .;l S ''

-. . _, ,1 ,. . i ss ' '' i w: x 1' .' U 1 '' ' ' X -'' - .- ' '

_',; ' .'; ", . ."'-.' ' .... ', ,'. i' ., .'_ ' ........... ',

'' ,.' a ,'; . '' . .,: ,'."',' : .,_

_; '-'.', .'-; ' _.' '. .'' '-_ s" '''k', '..-'',' ;' "S

o 5 s § .;.t ; - ,'',

-,:- - - - --I----- - - ^- - *^: - + : , , . . . ; - -,-,, - . W .

- - . , - ;.,, .. . -.;, , -,;.--. -

o B., v.-- . -D -- .,, , . ;. - .e.; ..- , - .. ;.- t ^ ; . ... .,, ., .. .. , ., ,... .

. . v .. . , - .- ;. , : .,, ;. i,- -- ,

. .................... ... . .. , . - . -,, s ........... .. ..

.: ., -, , .- , - . - - - i, - . . ., . ............. I

. - . . -- -- . . -,, - . ' --:--:; -; s l .f

:. ; ., .- ............... , , , ,, ,, ......... , - , %:, ... , .

' . . ! . : . . . ' ' . ? S ' t . ' . ' ', ' ', ' * + ' ' - ' ' . - . ' ' _ i t

II III &

lV

0.4 -1-

0.2 _ _ - . . i J- .

I

2

a

1 3 4

a) Radial fuel coordinate (mm)

1.2

0.

E

E

C)

0.

E

in

1.0

0.8

0.6

_I-I _

-4

0.4 -1- II

- . C,

. '-<..: .- .

.h . . .

.: #, , . '' -. ;,, ,

:'','lii - i: . -. _ 3,'; .

;,''. ,'ffi' ..,,..1

;: ', e

k

lV

0.2 -9-- _-

I

2 3

I

b) Radial fuel coordinate (mm)

Fig. C-13.5. (a) Radial Distribution of U238 Isotope and (b) Burnup for Fuel Rod #1113T (calculated)

C-137

I

APPENJ

I .1

TueI, Preirrit

D-1
Table D.W. Initial Characteristics of Refabricated Fuel Rods before IGR Reactor Tests.

Representative values

Characteristic Unit Value

1. Fuel (UOC,

1.1. Isotopic composition:

U23 % by weight see Table D.2.(1-2)

u238 % by weight see Table D.2.(1-2)

u236 % by weight 0.023

u234% by weight 0.057

1.2. Uranium impurity % by weight 0.152

1.3. Enrichment % see Table D.2.(1-2)

1.4. Oxygen coefficient per-unit not measured

1.5. Pellet outer diameter mm 7.56+0.01

1.6. Pellet inner diameter mm 2.2

1.7. Pellet height mm 9.8- 13

1.8. Density g/cm3 10.5 - 10.6

1.9. Grain size gm not measured

1.10. Fuel shape see Fig. D.2

1.11. Fuel macrostructure see Fig. D.1

1.12. Fuel microstructure see Fig. D.A

2. Cladding (Zr-1%Nb)

2.1. Outer diameter mm 9 11+0°1

2.2. Inner diameter mm not measured

2.3. Corrosion thickness Pim 5 -6

2.4. H2 content in cladding % by weight 3 - 6x10 3

2.5. Cladding microstructure see Fig. D.1

3. Fuel rod

3.1. Fuel rod design - see Fig. D.2

3.2. Fuel rod length mm 300

3.3. Initial fill pressure MPa 1.70.22

3.4. Gas composition:

He % by volume 97.57

Impurity % by volume 2.43

3.5. Free volume cm3 5.80 (average)

3.6. Fuel-cladding gap mm not measured

D-2
Pnoitinn 1

Fig. D.1. Typical Cross-Section Appearance, Cladding and Fuel Microstructure of Refabricated Fuel

Rod before IGR Reactor Test

D-3
1. Lower cap

2. Fixing ring

3. Fuel pellet

4. Connector

5. Upper plenum

6. Upper cap

Fuel pellet

6

L,, L2, Lo- individual values

for each fuel rod

(see Tables D.2.1, D.2.2)

Fig. D.2. Design Scheme of Refabricated Fuel Rod (Fresh fuel, Preirradiated cladding)

D-4.
ItifluMWiVracteristics of Refabnrcatd Fue Rods'

Table D.2.1. Consolidated List of Characteristics for Fuel Rods ## H14T, H15T, 1116T, H17T, H18T

Fuel rod number

Characteristic

H14T HIST H16T H17T H18T

1.1dentification number of commercial fuel 22 22 22 22 22

rods used for refabrication 2

2.Coordinates of commercial fuel rod sec- 1960 1500 2730 2150 1310

tions used for refabrication (from lower end 2110 1650 2880 2300 1460

of fuel rod) (mm)

3.Fuel stack length (mm) 141.0 142.0 141.0 141.0 141.0

33.0 25.7 25.8 19.4 24.7

4.Coordinates of fuel stack (mm) 174.0 167.7 166.8 160.4 165.7

5.Average section bum-up of commercial

fuel rod used for refabrication (MWd/kg U) 43.2 43A 42.3 43.2 44.1

6.Fuel isotopic composition:

U2.. (% weight) 4.47 4.47 4.47 4.46 4.46

U238 (% weight) 95.45 .95.45 95.45 95.46 95.46

7.Total fuel mass (g) 58.8 59.3 58.9 59.0 59.0

8.U235 mass in fuel (g) 2.31 2.33 2.31 2.31 2.31

9.Uranium isotopes mass (g) 51.7 52.1 51.7 51.8 51.8

I O.Enrichment (%) 4.47 4.47 4.47 4.46 4.46

l l.L, (see Fig. D.2) (mm) 13.6 6.3 6.4 0. 5.3

12.L1 (see Fig. D.2) (mm) 141.0 142.0 141.0 141.0 141.0

13.L, (see Fig. D.2) (mm) 5.5 11.8 12.7 19.1 13.8

14.Total gas volume (cm3 ) 5.74 5.69 5.73 5.73 5.72

15.Average outer diameter of cladding (mm) 9.10 9.10 9.12 9.10 9.10

16.Average fuel pellet diameter (mm) 7.57 7.56 7.56 7.57 7.57

D-5
Initial Individuai Cfiaraderistics of Refabricated Fuel Rods '

I (Fresh fuel, Priiri&3ag',cladding) '- . . _'' ' '

Table D.2.2. Consolidated List of Characteristics for Fuel Rods ## B19T, B20T, B21T, B22T, B23T

Fuel rod number

Characteristic

B19T B20T B21T B22T B23T

I.ldentification number of commercial fuel 22 22 22 22

rods used for refabrication

2.Coordinates of commercial fuel rod sections used for refabrication (from lower end 1270 3260 3450 690 3290270

of fuel rod) (mm) 1270 36 3409007

3.Fuel stack length (mm) 141.0 143.0 142.0 142.0 141.0

19.4 23.0 10.5* 10.5* 25.8

4.Coordinates of fuel stack (mm) 160.4 166.0 152.5* 152.5* 166.8

5.Average section bum-up of commercial l l

fuel rod used for refabrication (MWd/kg U) 43.7 38.4 29.7 42.8 41.8

6.Fuel isotopic composition:

U235 (% weight) 4.46 4.46 4.47 4.46 4.46

U238 (% weight) 95.46 95.46 95.45 95.46 95.46

7.Total fuel mass (g) 59.0 59.5 59.1 58.9 58.9

8.U235 mass in fuel (g) 2.31 2.33 2.32 2.31 2.31

9.Uranium isotopes mass (g) 51.8 52.2 51.9 51.8 51.8

1O.Enrichment (%) 4.46 4.46 4.47. 4.46 4.46

1 1.L1 (see Fig. D.2) (mm) 0. 3.6 0.* 0.* 6.4

12.L,2 (see Fig. D.2) (mm) 141.0 143.0 142.0 142.0 141.0

13.Li (see Fig. D.2) (mm) 19.1 13.5 27.0* 27.0* 12.7

14.Total gas volume (cm3) 5.72 5.67 6.12 6.14 5.73

15.Average outer diameter of cladding (mm) 9.11 9.12 9.11 9.11 9.12

16.Average fuel pellet diameter (mm) 7.56 7.56 7.56 7.56 7.56

T he fixing ring is absent in the fuel rod

D-6
| Initial ndiv rduailCharacteristics of Refabricated Fuel Rods -

(Fres hfu6 liradiated cladding). - . . - . : - . -i

Table D.3. Free Gas Volume in Refabricated Fuel Rods before IGR Reactor Tests for Axial Coordinates 185+295 mm

Axial coordinate Free gas volume

from lower end (mm3 )

of fuel rod

(mm) H14TUH5T 1116T H17T H18T B19T B20T B21T B22T B23T

185 53 53 53 53 53 53 53 53 53 53

195 71 71 71 71 71 71 71 71 71 71

205 250 250 250 250 250 250 250 250 250 250

215 468 468 468 468 468 468 468 468 468 468

225 468 468 468 468 468 468 468 468 468 468

235 468 468 468 468 468 468 468 468 468 468

245 468 468 468 468 468 468 468 468 468 468

255 468 468 468 468 468 468 468 468 468 468

265 468 468 468 468 468 468 468 468 468 468

275 468 468 468 468 468 468 468 468 468 468

285 119 119 119 119 119 119 119 119 119 119

295 0 0 0 0 0 0 0 0 0 0

D-7
I

I
:

APP-E!

duallarac

D-9
#H14T Initial Individual Cliwactristics of Refabricated Fuel Rods I (Fresh fuel, Preirra& d cladding) ; - :-

Table D-1.1. Individual Initial Characteristics for Fuel Rod #H14T (measured)

Axial coordi- Cladding outer diameter Fuel stack Fuel Linear fuel Free gas

nate from (mm) average mass mass volume

lower end of diameter (g)* (g/cm)* (mm 3

)* 3)

fuel rod - 00 90° 1 average (mm)*

(mm) I__

5

10

15

20

25

30

351)

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

165

170

1752)

180

9.098

9.101

9.099

9.100

9.091

9.081

9.082

9.088

9.091

9.090

9.088

9.091

9.099

9.101

9.098

9.088

9.082

9.088

9.094

9.083

9.087

9.088

9.088

9.087

9.089

9.098

9.107

9.109

9.101

9.092

9.099

9.092

9.097

9.093

9.103

9.101

9.092

9.100

9.105

9.110

9.112

9.097

9.105

9.105

9.103

9.103

9.099

9.105

9.116

9.121

9.128

9.134

9.121

9.121

9.115

9.111

9.116

9.121

9.10

9.10

9.10

9.10

9.09

9.09

9.09

9.09

9.10

9.10

9.10

9.10

9.10

9.10

9.10

9.10

9.09

9.09

9.10

9.10

9.10

9.11

9.11

9.10

9.11

9.11

9.11

9.11

9.11

7.57

7.57

7.57

7.57

7.57

7.57

7.57

7.57

7.57

7.57

7.56

7.56

7.56

7.56

7.57

7.57

7.57

7.57

7.57

7.57

7.57

7.57

7.57

7.57

7.56

7.56

7.56

7.56

7.56

0.0

0.0

0.0

0.0

0.0

0.0

1.88

2.09

2.09

2.08

2.08

2.06

2.06

2.07

2.08

2.08

2.08

2.08

2.09

2.09

2.09

2.09

2.09

2.08

2.08

2.07

2.07

2.08

2.08

2.09

2.10

2.10

2.11

2.12

0.63

0.0

0.0

0.0

0.0

0.0

0.0

0.0

4.17

4.17

4.17

4.17

4.16

4.12

4.12

4.15

4.15

4.16

4.16

4.16

4.18

4.18

4.18

4.18

4.17

4.16

4.16

4.14

4.14

4.16

4.16

4.18

4.21

4.21

4.22

4.24

4.22

0.0

8.8

98.9

234.0

234.0

199.7

183.6

51.0

36.2

36.4

36.4

36.9

38.7

38.7

37.4

37.2

37.0

36.8

36.7

36.0

36.0

36.0

36.0

36.3

36.7

36.8

37.7

37.7

37.1

36.8

36.1

34.6

34.6

33.8

33.1

174.0

114.8

* These numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate + 2.5 mm

|) Inilial coordinate of fuel is 33 mm

2) End point coordinate of fuel is 174 mm

3) Free gas volume for coordinates 185-295 mm is presented in Table D.3

D-10
#H14T Initiaindi ind! Characteristics of Refabricated Fuel Rods |

(Frish fuel radiated cladding) '. , - ., . , , .

9.4

oI

E

E

I.

w

0

on~

la

9.3

9.2

9.1

., ..

'

9.0 I 6 I I I I I I -

0 50 100

a)

150 200 250

Axial coordinate (mm)

ME

b)

n

.r i

E

E

0

0 50 100 150 200 250

c) Axial coordinate, mm

Fig. D-1.1. (a) Results of Profilometry, (b) Radiography, (c) Axial Fuel Mass Distribution and Axial

Free Gas Volume Distribution for Fuel Rod #114T

D-11

i.,.APPENDIX l

Initial Individual. Characteristic 7 ., ' ', £,, . , , i' 1-A..f, ,@-

,;,,he,; 8;'!. i',< t' o; r.H.

'... '';.; .''' I.',',.'. -' ' .,:;' .... ' .:

.: ., ... :, ',.-.,.''.,,'., . " ,, .. :'

vueiRod HISIX' '' ...'-':-' S _. .,,, ,,, '; ',,, -,: ., . ' > ' ' .................................................. .! . .- .' .

Ai ,' ' ;, ' ', '>,', '> '.' - ' i a: ' . ''',;' . . t _ ' '' ' . .

D-13
Initial Individual C1i0Fristics of Refabricated Fuel Rods'-' -I

Ta #HST. 'ffesi':fuil,-PteiriJt , 'adding) ':' '-. : ' -", "';'.'"*-; "Jr 111 5T fo I. R (

Table D-2.1. Individual Initial Charactcristics for Fuel Rod #H15T (measured)

Axial coordi- Cladding outer diameter Fuel stack Fuel Linear fuel Free gas

nate from (mm) average mass mass volume

lower end of diameter (g)* (g/cm)* (mm3 )*3)

fuel rod 00900 average (mm)*

(mm) I aeg

5 0.0 0.0 8.8

10 0.0 0.0 98.9

15 0.0 0.0 227.0

20 - - - - 0.0 0.0 183.6

25') 9.097 9.105 9.1 7.57 0.76 4.21 129.9

30 9.094 9.101 9.10 7.57 2.11 4.21 34.4

35 9.095 9.094 9.09 7.57 2.11 4.21 34.4

40 9.097 9.094 9.10 7.56 2.09 4.18 36.2

45 9.096 9.095 9.10 7.56 2.09 4.17 36.2

50 9.101 9.099 9.10 7.56 2.09 4.18 35.8

55 9.104 9.102 9.10 7.56 2.09 4.19 35.6

60 9.100 9.097 9.10 7.56 2.09 4.18 35.7

65 9.097 9.106 9.10 7.55 2.09 4.18 36.1

70 9.093 9.103 9.10 7.55 2.09 4.18 36.1

75. 9.093 9.104 9.10 7.56 2.08 4.17 36.4

80 9.089 9.103 9.10 7.56 2.08 4.17 36.5

85 9.098 9.095. 9.10 7.57 2.09 4.17 36.2

90 9.098 9.092 9.10 7.57 2.09 4.18 35.9

95 9.093 9.098 9.10 7.57 2.09 4.18 36.0

100 9.090 9.099 9.09 7.57 2.07 4.15 37.6

105 9.090 9.110 9.10 7.57 2.07 4.15 37.6

110 9.091 9.114 9.10 7.57 2.09 4.18 36.0

115 9.090 9.112 9.10 7.57 2.10 4.19 35.2

120 9.085 9.114 9.10 7.57 2.08 4.17 36.5

125 9.086 9.111 9.10 7.57 .2.07 4.13 38.2

130 9.088 9.101 9.09 7.57 2.07 4.13 38.1

135 9.091 9.093 9.09 7.57 2.08 4.17 36.5

140 9.086 9.086 9.09 7.57 2.08 4.17 36.5

145 9.083 9.092 9.09 7.56 2.08 4.17 36.5

150 9.084 9.104 9.09 7.56 2.08 4.17 36.4

155 9.089 9.106 9.10 7.56 2.09 4.18 36.2

160 9.090 9.109 9.10 7.57 2.10 4.19 35.4

165 9.094 9.102 9.10 7.57 2.10 4.21 34.6

1702) 9.098 9.101 9.10 7.57 0.08 4.19 226.1

175 - - - - 0.0 0.0 234.0

180 0.0 0.0 114.8

' These numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate ±L2.5 mm

IInitial coordinate of fuel is 25.7 mm

2) End point coordinate of fuel is 167.7 mm

3) Free gas volume for coordinates 185-295 mm is presented in Table D.3

D-14
I#H15T IInitial Indf-V ~haracteristics of Refabricaited Fuel Rods U L

(FreshfuelieQ iated cladding) -:; - ' '--" :' "' -|

9.4 .T.

-

c)

E

0

0

te

3-

- .

- . 90 I- 9.:4.4 + -1*-

I

7F 1 1 1 1

9 I -1

9s.\I I II . ; . . I , II I a

0 50 100

a)

150 200 250

Axial coordinatc (mm)

__-~I-~ M=m

b)

. Ah

E

U

E

c4

4. 80

3 - 60

2 - .40

.................... .... ...... ..* . I . e... . .....

0 - ~ - 0~~~- 

IE

0

0 50 100

C)

150 200

Axial coordinate, mm

250

Fig. D-2.1. (a) Rcsults of Profllometry, (b) Radiography, (c) Axial Fuel Mlass Distribution and Axial

Free Gas Volume Distribution for Fuel Rod #lh15T

D-15

I; '1 ;v-; IniotiA ,,,.Sal

v

_ APP'.'. ,-- , .'END'

ual CharactMer <4 2

'uelRod#711624

D-17
#H16T 'Initial Individual Chiartaedstics of Refabricated Fuel Rods , .

| (Fresh fuel, Preiriari ilaadding) .- .

Table D-3.1. Individual Initial Characteristics for Fuel Rod #H16T (measured)

Axial coordi- Cladding outer diameter Fuel stack Fuel Linear fuel Free gas

nate from (mm) average mass mass volume

lower end of diameter (g)* (g/cm)* (mm 3

)* 3 )

fuel rod 00 900 average (mm)*

(mm) I I

5

10

15

20

25')

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

1652)

170

175

180

9.108

9.115

9.122

9.121

9.126

9.123

9.129

9.121

9.109

9.105

9.107

9.112

9.099

9.117

9.108

9.105

9.099

9.097

9.107

9.117

9.120

9.121

9.122

9.122

9.105

9.106

9.102

9.096

9.093

9.119

9.113

9.111

9.120

9.123

9.127

9.124

9.129

9.143

9.139

9.146

9.155

9.133

9.149

9.144

9.141

9.133

9.142

9.145

9.147

9.149

9.145

9.131

9.123

9.112

9.112

9.114

9.121

9.100

9.11

9.11

9.12

9.12

9.12

9.13

9.13

9.13

9.13

9.12

9.13

9.13

9.12

9.13

9.13

9.12

9.12

9.12

9.13

9.13

9.13

9.13

9.13

9.12

9.11

9.11

9.11

9.11

9.10

7.57

7.57

7.57

7.57

7.57

7.56

7.56

7.56

7.55

7.55

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.57

7.57

7.57

7.57

7.57

7.57

7.57

0.0

0.0

0.0

0.0

0.71

2.08

2.08

2.07

2.07

2.08

2.08

2.09

2.10

2.10

2.09

2.09

2.09

2.09

2.09

2.11

2.11

2.10

2.10

2.10

2.10

2.10

2.08

2.08

2.08

2.08

2.07

2.05

1.77

0.0

0.0

0.0

0.0

0.0

0.0

0.0

4.16

4.16

4.16

4.15

4.15

4.16

4.16

4.17

4.20

4.20

4.19

4.19

4.18

4.17

4.18

4.22

4.22

4.20

4.19

4.20

4.20

4.19

4.17

4.17

4.17

4.16

4.14

4.09

4.12

0.0

0.0

0.0

8.8

98.9

228.0

183.6

133.8

37.1

37.1

37.4

37.4

37.0

36.7

36.2

34.8

34.8

35.5

35.6

36.0

36.3

35.9

34.1

34.1

35.1

35.3

35.2

35.1

35.3

36.5

36.5

36.6

36.7

37.7

40.0

66.3

234.0

234.0

114.8

* These numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate ± 2.5 mm

I) Initial coordinate of fuel is 25.8 mm

2) End point coordinate of fuel is 166.8 mm

3) Free gas volume for coordinates 185-295 mm is presented in Table D.3

D-18
#H16T Inidalindivi Chaiacteristics of Refabricated Fuel Rods --

(Fresh fueradiated cladding) -; . ; .-

9,

c>

E

I-.2

O

9

.20

to

. E

9,

9.

.4.

.2

. ..... ~f

.0* ll .. 

9

9.

0 50 100

a)

150 200 250

Axial coordinate (mm)

M"I

b)

ivm

2

E

cs

a

4- -80

3 60

_ r z ~~~~..... ................. ..._

2 -40

- .-- T -20

O. . : -_..._. ........

0- -r - I

2

0

0 50 100 150 - 200 250

c) Axial coordinate, mm

Fig. D-3.1. (a) Results of Profilometry, (b) Radiography, (c) Axial Fuel Mass Distribution and Axial

Free Gas Volume Distribution for Fuel Rod #1116T

D-19
iIIIi

I

i

I
D-21
nI~tiafIn~d a Chact sof Refabricat& Fuci Rd i #H17T I fia __ I 

Table D-4.1. Individual Initial Characteristics for Fuel Rod #H17T (measured)

Axial coordi- Cladding outer diameter Fuel stack Fuel Linear fuel Free gas

nate from (mm) average mass mass volume

lower end of , diameter (g)* (g/cm)* (mm3)*l)

fuel rod 00 900 average (mm)*

(mm) I____ J m)

5 0.0 0.0 8.8

10 0.0 0.0 78.7

15 - - - - 0.0 0.0 183.6

20') 9.093 9.110 9.10 7.57 1.30 4.21 91.3

25 9.101 9.103 9.10 7.57 2.10 4.21 34.7

30 9.108 9.108 9.11 7.57 2.10 4.20 35.1

35 9.101 9.110 9.11 7.57 2.09 4.17 36.4

40 9.091 9.116 9.10 7.57 2.09 4.17 36.4

45 9.087 9.113 9.10 7.56 2.09 4.19 35.5

50 9.096 9.101 9.10 7.56 2.09 4.19 35.5

55 9.100 9.104 9.10 7.56 2.10 4.21 34.7

60 9.100 9.099 9.10 7.57 2.11 4.22 . 34.1

65 9.117 9.096 9.11 7.56 2.10 4.20 35.1

70 9.110 9.093 9.10 7.56 2.07 4.14 37.9

75 9.112 9.090 9.10 7.56 2.07 4.14 37.9

80 9.110 9.086 9.10 7.57 2.07 4.15 37.5

85 9.101 9.096 9.10 7.57 2.07 4.15 37.5

90 9.104 9.096 9.10 7.57 2.09 4.17 36.2

95 9.093 9.110 9.10 7.57 2.10 4.20 35.0

100 9.101 9.103 9.10 7.57 2.10 4.20 35.0

105 9.108 9.108 9.11 7.57 2.10 4.20 35.1

110 9.101 9.110 9.11 7.57 '2.10 4.20 35.1

115 9.091 9.116 9.10 7.57 2.09 4.18 35.9

120 9.087 9.113 9.10 7.57 2.09 4.18 36.2

125 9.096 9.101 9.10 7.56 2.10 4.19 35.2

130 9.100 9.104 9.10 7.57 . 2.11 4.22 34.1

135 9.100 9.099 9.10 7.57 2.11 4.22 34.2

140 9.117 9.096 9.11 7.57. 2.10 4.20 34.9

145 9.110 9.093 9.10 7.57 2.10 4.20 34.9

150 9.112 9.090 9.10 . 7.57 - 2.06 4.12 38.5

155 9.110 9.086 9.10 7.57 2.01 4.03 43.1

1602) 9.101 9.096 9.10 7.57 1.19 4.11 121.2

165 -- - - 0.0 0.0 234.0

170 0.0 0.0 234.0

175 0.0 0.0 234.0

.180 0.0 0.0 114.8

* These numerical values orcharacteristics are presented as average values at the length interval equal to the axial coordinate * 2.5 mm

I)Initial coordinate or fuel is 19.4 num

2) End point coordinate of fuel is 160.4 nun

3) Free gas volume for coordinates 185-295 mm is presented in Table D.3

D-22
HH17T 1 sticsofRcfabicatcd Fuel Rxsv

I;F _ claddin)-<* sPs-;Z r- -h>S< If

9.4

E

0

~aU

0

to

._

la

9.3

9.2

*. - fl.F.- . ..

_.

I .... . I 

- = -I a II I a I I

9.1

9.0

0 50 100

a)

150 200 250

Axial coordinate (mm)

M-I-U,

b)

. An,

9

.10

el SO

)

U

P

.1 - ____ -60___

2- -40

1 _ - 20

- . ........ . . n

I 5nI 

0

v I I I

0 50 100

C)

150 200

Axial coordinate, mm

250

Fig. D4.1. (a) Results of Profilometry, (b) Radiography, (c) Axial Fuel Mass Distribution and Axial

Free Gas Volume Distribution for Fuel Rod #1117T

D-23

_ . . _
i

I
D-25
#H18T riInil ,dii tcs of Refabricaitd Fuel Ro's" '

(cifuc, ' - ? iding); 

Table D-5.1. Individual Initial Characteristics for Fuel Rod #H18T (measured)

Axial coordi- Cladding outer diameter Fuel stack Fuel Linear fuel Free gas

nate from (mm) average mass mass volume

lower end of diameter (g)* (g/cm)* (mm 3 )* 3

)

fuel rod 00 900 average (mm)*

(mm) I__ __ 

I I I (mm)I*

S

10

15

20

25')

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

1652)

170

175

180

9.116

9.106

9.096

9.092

9.112

9.116

9.102

9.114

9.112

9.111

9.104

9.093

9.087

9.085

9.089

9.091

9.098

9.101

9.099

9.105

9.100

9.092

9.095

9.096

9.099

9.094

9.103

9.105

9.098

9.118

9.119

9.128

9.123

9.114

9.123

9.116

9.111

9.110

9.115

9.119

9.127

9.120

9.113

9.111

9.102

9.110

9.117

9.102

9.098

9.095

9.099

9.101

9.092

9.100

9.106

9.099

9.094

9.096

9.12

9.11

9.11

9.11

9.11

9.12

9.11

9.11

9.11

9.11

9.11

9.11

9.10

9.10

9.10

9.10

9.10

9.11

9.10

9.10

9.10

9.10

9.10

9.09

9.10

9.10

9.10

9.10

9.10

7.56

7.56

7.56

7.56

7.57

7.57

7.57

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.57

7.57

7.57

7.57

7.57

7.57

7.57

7.57

7.57

7.57

7.57

0.0

0.0

0.0

0.0

1.16

2.08

2.09

2.13

2.13

2.10

2.09

2.08

2.08

2.08

2.11

2.11

2.09

2.08

2.08

2.08

2.08

2.10

2.10

2.10

2.10

2.09

2.09

2.09

2.09

2.09

2.08

2.06

. 1.32

0.0

0.0

0.0

0.0

0.0

0.0

0.0

4.16

4.16

4.18

4.25

4.25

4.19

4.17

4.17

4.16

4.16

4.22

4.22

4.18

4.17

4.17

4.17

4.17

4.21

4.21

4.20

4.19

4.18

4.17

4.17

4.17

4.17

4.15

4.12

4.14

0.0

0.0

0.0

8.8

98.9

216.9

183.6

101.4

36.9

36.1

32.5

32.5

35.4

36.2

36.5

36.9

36.7

34.1

34.1

35.9

36.5

36.5

36.5

36.5

34.7

34.6

35.1

35.4

35.7

36.3

36.3

36.3

36.3

37.3

38.8

108.5

234.0

234.0

114.8 .5. 5 1 .5. 1 £

* These numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate i 2.5 mm

I) Initial coordinate offuel is 24.7 mm

2) End point coordinate or fuel is 165.7 mm

3) Free gas volume for coordinates 185-295 mm is presented in Table D.3

D-26
I

. #H18T patof Refabricated Fuel Rods,2 I

,I el rma id clidding) -' '-'

E

S.-E

c)

.I

la1

4)

0

on

.5IC

0 50 100 150 200 250

a) Axial coordinate (mm)

b)

5 100

0

0 50 100 150 200 250

c) Axial coordinate, mm

Fig. D-5.1. (a) Results of Profilometry, (b) Radiography, (c) Axial Fuel Mass Distribution and Axial

Free Gas Volume Distribution for Fuel Rod #1118T

D-27
i
D-29
#B19T Tan~i~Ii1Ca li~sofRefabricacd Fuel t| | ngye~Z"cda4-,; " * - _- A

Table D-6.1. Individual Initial Characteristics for Fuel Rod NB19T (measured)

Axial coordi- Cladding outer diameter Fuel stack Fuel Linear fuel Free gas

nate from (mm) average mass mass volume

lower end of diameter (g)* (g/cm)* (mm 3

)*3 )

fuel rod 00 900 average (mm)*

(mm) __ 

I I_ _- _ _ _ _

5

10

15

20')

25

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

1602)

165

170

175

180

9.099

9.103

9.101

9.089

9.092

9.104

9.104

9.099

9.093

9.094

9.095

9.087

9.086

9.091

9.100

9.098

9.092

9.085

9.089

9.092

9.089

9.094

9.085

9.098

9.100

9.106

9.113

9.110

9.117

9.108

9.106

9.107

9.111

9.110

9.106

9.104

9.108

9.111

9.114

9.110

9.123

9.122

9.121

9.112

9.108

9.123

9.136

9.139

9.139

9.135

9.144

9.141

9.124

9.115

9.123

9.130

9.130

9.138

9.10

9.10

9.10

9.10

9.10

9.11

9.10

9.10

9.10

9.10

9.10

9.11

9.10

9.11

9.11

9.10

9.11

9.11

9.11

9.12

9.11

9.12

9.11

9.11

9.11

9.11

9.12

9.12

9.13

7.57

7.57

7.57

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.57

7.57

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

0.0

0.0

0.0

1.30

2.09

2.09

2.10

2.10

2.08

2.08

2.08

2.08

2.09

2.11

2.11

2.07

2.07

2.08

2.10

2.10

2.10

2.10

2.11

2.12

2.11

2.09

2.09

2.08

2.08

2.08

2.09

1.21

0.0

0.0

* 0.0

0.0

0.0

0.0

0.0

4.18

4.18

4.18

4.19

4.19

4.16

4.16

4.16

4.16

4.17

4.22

4.22

4.15

4.13

4.16

4.19

4.19

4.19

4.19

4.23

4.24

4.22

4.18

4.18

4.16

4.16

4.17

4.18

4.17

0.0

0.0

0.0

0.0

8.8

78.7

183.6

92.0

35.9

35.7

35.3

35.3

36.7

36.9

36.9

36.9

36.4

34.1

34.1

37.4

38.1

36.9

35.4

35.4

35.3

35.3

33.6

33.1

34.3

35.7

35.8

37.1

37.1

36.6

36.0

119.4

234.0

234.0

* 234.0

114.8

* These numerical values or characteristics are presented as average values at the length interval equal to the axial coordinate ± 2.5 mm

I) Initial coordinate of fuel is 19.4 mm

2) End point coordinate of fuel is 160.4 mm

3) Free gas volume for coordinates IS5-295 mm is presented in Table D.3

D-30
#B19T I, _~Zlof Re~jc~ fabrkicatdFuel Rodsl~~-.

cld i ) I .-- - '~

9.4

I-

~U

0a.

co

ca

._

9.3

9.2

.I....

. .... .*e

--^G--X

_ l Il

9.1

9.0

0 50 100

a)

150 200 250

Axial coordinate (mm)

b)

5

c

2

U

t.;

2-

0

0 50 100 150 200 250

c) Axial coordinate, mm

Fig. D-6.1. (a) Results of Profilometry, (b) Radiography, (c) Axial Fuel Mass Distribution and Axial

Free Gas Volume Distribution for Fuel Rod #B19T

D-31

D-33
#B20T | of Refabricated Fuel RodsO

|(Frsh ftiei~g1 _ Eding) t ;. . ..............

Table D-7.1. Individual Initial Characteristics for Fuel Rod B2OT (measured)

Axial coordi- Cladding outer diameter Fuel stack Fuel Linear fuel Free gas

nate from (mm) average - mass mass volume

lower end of diameter (g)* (g/cm)* (mm3)*3)

fuel rod 00 900 | average (mm)*

(mm) I__ __ _ _ _I_

5

10

15

20

25)

30

35

40

45

50

55

60

65

70

75.

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

1652)

170

175

180

9.121

9.122

9.112

9.110

9.109

9.113

9.125

9.128

9.132

9.132

9.131

9.137

9.131

9.127

9.130

9.134

9.134

9.129

9.130

9.137

9.138

9.122

9.134

9.134

9.134

9.132

9.117

9.121

9.118

9.120

9.114

9.110

9.113

9.107

9.104

9.113

9.118

9.125

9.140

9.136

9.116

9.120

9.121

9.117

9.123

9.119

9.123

9.120

9.110

9.121

9.114

9.113

9.117

9.104

9.102

9.120

9.120

9.116

9.12

9.12

9.11

9.11

9.11

9.11

9.12

9.12

9.13

.9.14

9.13

9.13

9.13

9.12

9.12

9.13

9.13

9.13

9.13

9.12

9.13

9.12

9.12

9.13

9.12

9.12

9.12

9.12

9.12

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.57

7.57

7.57

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.57

7.57,

7.57

7.57

7.57

7.57

7.57

7.57

7.57

7.57

0.0

0.0

0.0

0.0

1.88

2.09

2.09

2.10

2.09

2.06

2.06

2.10

2.11

2.09

2.06

2.06

2.08

2.08

2.09

2.10

2.10

2.08

2.08

2.08

2.08

2.08

2.07

2.07

2.04

2.04

2.06

2.10

1.45

0.0

0.0

0.0

0.0

0.0

0.0

0.0

4.18

4.18

4.19

4.20

4.18

4.13

4.13

4.20

4.22

4.17

4.12

4.12

4.15

4.15

4.18

4.20

4.19

4.17

4.17

4.17

4.17

4.15

4.14

4.13

4.08

4.08

4.13

4.20

4.15

0.0

0.0

0.0

8.8

98.9

199.7

183.6

50.6

35.8

35.5

35.2

36.0

38.5

38.5

35.0

34.2

36.2

38.9

38.9

37.2

37.2

35.7

35.0

35.4

36.4

36.4

36.5

36.5

37.2

37.8

38.2

40.9

40.9

38.4

35.0

96.5

234.0

234.0

114.8

l These numerical values ofcharacteristics are presented as average values at the length interval equal to the axial coordinate ± 2.5 mm

1) Initial coordinate offuel is 23.0 mm

2) End point coordinate offuel is 166.0 mm

3) Free gas volume for coordinates 185-295 mm is presented in Table D.3

D-34
f 

#B20T | ii~ s of Refabricated Fuel Rods - , ' claddingi), Izj - ;' .

9.4

IE

2

c)

0

00

ba

9.3

9.2

I I

9.1

9.0 -I I I - I -I0 50 100

a)

150 200

Axial coordinate (mm)

250

b)

5

4

i)

2

4)

3

2

'J'N ----------I ga

80

60

-~ -40

T. _ 0 ,= * h

0

1

.. . ....... ._.., ....... .. ......... . ...... .. FI i.......

0 0

I

0 50 100

c)

150 200 250

Axial coordinate, mm

Fig. D-7.1. (a) Results of Profilometry, (b) Radiography, (c) Axial Fuel Mass Distribution and Axial

Free Gas Volume Distribution for Fuel Rod #1B20T

D-35

D-37
#B21T I lmdW S4ra hratrlics of Refatricat& Fuel R~dS>; | | (,

Table D-8.1. Individual Initial Characteristics for Fuel Rod #B21T (measured)

Axial coordi- Cladding outer diameter Fuel stack Fuel Linear fuel Free gas

nate from (mm) average mass mass volume

lower end of diameter (g)* (g/cm)* (mm 3)*3)

fuel rod 00 average (mm)*

(mm)

5

15

20

25

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

1502)

155

160

165

170

175

180

9.107

9.110

9.108

9.113

9.105

9.112

9.120

9.110

9.110

9.111

9.105

9.111

9.103

9.096

9.095

9.103

9.111

9.109

9.106

9.120

9.121

9.107

9.107

9.113

9.119

9.125

9.109

9.107

9.105

9.107

9.108

9.108

9.116

9.110

9.103

9.099

9.119

9.122

9.115

9.112

9.112

9.115

9.108

9.101

9.099

9.096

9.104

9.113

9.109

9.109

9.115

9.117

9.108

9.106

9.110

9.112

9.112

9.106

9.11

9.11

9.11

9.11

9.11

9.11

' 9.11

9.11

9.12

9.11

9.11

9.11

9.11

9.10

9.10

9.10

9.10

9.11

9.11'

9.11

9.12

9.11

9.11

9.11

9.11

9.12

9.11

9.11

9.11

7.57

7.57

7.57

7.57

7.57

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

0.0

0.83

2.08

2.08

2.09

2.09

2.07

2.06

2.08

2.10

2.10

2.08

2.08

2.09

2.10

2.10

2.10

2.10

2.09

2.09

2.08

2.08

2.08

2.07

2.07

2.06

2.06

2.06

2.08

2.09

0.0

0.0

0.0

0.0

0.0

0.0

0.0

4.16

4.16

4.17

4.18

4.18

4.14

4.13

4.15

4.21

4.21

4.16

4.16

4.18

4.20

4.20

4.20

4.20

4.18

4.17

4.17

4.16

4.16

4.14

4.14

4.12

4.11

4.13

4.16

4.19

0.0

0.0

0.0

0.0

0.0

0.0

8.8

20.0

36.7

36.6

35.8

35.8

37.8

38.5

37.2

34.6

34.6

36.8

36.8

35.8

35.2

35.2

35.2

35.2

36.1

36.3

36.5

36.8

36.9

38.0

38.0

38.8

39.1

38.5

37.0

35.5

234.0

234.0

234.0

234.0

234.0

114.8

* These numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate i 2.5 mm

I) Initial coordinate orfuel is io.5 mm (in the fuel rod design scheme absent the fixing ring)

2) End point coordinate of fuel is 152.5 mm

3) Free gas volume for coordinates 185-295 mm is presented in Table D.3

D-38
#B21T Inki~cersico ifabriC`3tc Fuel A od I" - ~r ~CladdIng) w ; ."

9.

I)

S.0

0

la

'9

Uo

9.3

9.2

9.1

9.0

0 50 100 150 200

a) Axial coordinate (mm)

250

b)

5 . . . .I IF Ir

fil I

I *-------- gas ]

4

0

2

3

2

........... 1*_.

-.. ...

. S ...... ..........

80

60 E

40 6

0

20

0

. I

I

0

0 50 100

c)

150 200 250

Axial coordinate, mm

Fig. D-8.1. (a) Results of Profilometry, (b) Radiography, (c) Axial Fuel Mass Distribution and Axial

Free Gas Volume Distribution for Fuel Rod #B21T

D-39
li
D41
#B22T | Tni6fkbcfabucated Fuel d : |

1(Frag. Chi~. ding)th sA

Td .Co l. , iTable D-9.1. Individual Initial Characteristics for Fuel Rod #B22T (measured)

Axial coordi- Cladding outer diameter Fuel stack Fuel Linear fuel Free gas

nate from (mm) average mass mass volume

lower end of diameter (g)* (g/cm)* (mm3 )*3)

fuel rod 00 900 average (mm)*

(m m ) _ _ I - _ I _ __ __ __

5

lo,

15

20

25

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

1502)

155

160

165

170

175

180

9.096

9.098

9.101

9.107

9.105

9.105

9.117

9.120

9.124

9.119

9.105

9.103

9.103

9.104

9.105

9.117

9.119

9.121

9.116

9.100

9.103

9.104

9.107

9.106

9.105

9.117

9.119

9.114

9.115

9.109

9.111

9.112

9.102

9.105

9.117

9.114

9.110

9.109

9.098

9.107

9.111

9.104

9.118

9.118

9.117

9.116

9.103

9.103

9.103

9.105

9.107

9.102

9.096

9.098

9.098

9.093

9.089

9.089

9.10

9.10

9.11

9.10

9.11

9.11

9.12

9.12

9.12

9.11

9.11

9.11

9.10

9.11

9.11

9.12

9.12

9.11

9.11

9.10

9.10

9.11

9.10

9.10

9.10

9,11

9.11

9.10

9.10

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.57

7.57

7.57

7.57

7.56

7.55

7.55

7.56

7.56

7.57

7.57

7.57

7.57

7.57

7.57

7.57

7.57

7.57

7.56

7.56

7.56

0.0

0.83

2.09

2.09

2.07

2.07

2.07

2.08

2.08

2.09

2.09

2.08

2.08

2.08

2.07

2.07

2.07

2.07

2.08

2.08

2.08

2.07

2.07

2.08

2.08

2.07

2.07

2.07

2.07

2.07

0.0

0.0

0.0

0.0

0.0

0.0

0.0

4.17

4.17

4.17

4.14

4.14

4.15

4.16

4.16

4.17

4.17

4.17

4.17

4.15

4.14

4.14

4.13

4.13

4.15

4.16

4.15

4.15

4.15

4.16

4.16

4.14

4.13

4.13

4.13

4.13

0.0

0.0

0.0

0.0

0.0

0.0

8.8

19.8

36.2

36.3

38.1

38.1

37.4

37.0

36.7

36.2

36.2

36.5

36.5

37.3

37.7

37.8

38.2

38.2

37.3

36.9

37.2

37.6

37.6

37.0

37.0

37.8

38.2

38.2

38.2

38.2

234.0

234.0

234.0

234.0

234.0

114.8

* These numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate i 2.5 mm

1) Initial coordinate of fuel is 10.5 mm (in the fuel rod design scheme absent the fixing ring)

2) End point coordinate of fuel is 152.5 mm

3) Free gas volume for coordinates 185-295 mm is presented in Table D.3

D-42
#B22T ;au>Ci;Tcieistics of Refabicad 1ueI Ro * a. _SMecadg. H si;- ................ I,4t

.i.

*S

0

I._l

.to

.q

C0

C>

U

C)

.E

9.4 -=={__

_ I 00

9.2-

9.1-.

9.00

0 50 100 150 200 250

a) Axial coordinate (mm)

b)

4 80

3- 60

2,_.;...__.....,_;_......_.._...........,.... ...... '2

- T40

1 *- 20

.... . f... . .............. .......... .....

E

I

0

0

0 50 100

c)

150 200

Axial coordinate, mm

250

Fig. D-9.1. (a) Results of Profilometry, (b) Radiography, (c) Axial Fuel Mass Distribution and Axial

Free Gas Volume Distribution for Fuel Rod #B22T

D-43

D45
#B23T I,(Frh C in fi - a'd Fuel od>

Table ; -. d, 

Table D-10.1. Individual Initial Characteristics for Fuel Rod #B23T (measured)

Axial coordi- Cladding outer diameter Fuel stack Fuel Linear fuel Free gas

nate from (mm) average mass mass volume

lower end of diameter (g)* (g/cm)* (mm 3 )* 3

)

fuel rod 00 900 1average (mm)*

(mm) __ _ _ 

I I m)

5

10

15

20

25')

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

1652)

170

175

180

9.096

9.099

9.097

9.098

9.097

9.101

9.109

9.110

9.105

9.111

9.110

9.112

9.113

9.112

9.104

9.101

9.099

9.093

9.090

9.093

9.104

9.110

9.111

9.122

9.116

9.115

9.113

9.106

9.109

9.142

9.132

9.114

9.119

9.136

9.140

9.130

9.138

9.142

9.134

9.134

9.120

9.105

9.106

9.110

9.106

9.120

9.121

9.126

9.130

9.123

9.128

9.121

9.121

9.118

9.125

9.138

9.138

9.125

9.12

9.12

9.11

9.11

9.12

9.12

9.12

9.12

9.12

9.12

9.12

9.12

9.11

9.11

9.11

9.10

9.11

9.11

9.11

9.11

9.11

9.12

9.12

9.12

9.12

9.12

9.13

9.12

9.12

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.57

7.57

7.57

7.57

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

0.0

0.0

0.0

0.0

0.71

2.08

2.08

2.09

2.09

2.08

2.08

2.08

2.09

2.09

2.10

2.10

2.10

2.10

2.09

2.07

2.07

2.09

* 2.09

2.09

2.08

2.09

2.11

2.11

2.12

2.12

2.09

* 2.05

1.78

0.0

0.0

0.0

0.0

0.0

0.0

0.0

4.17

4.17

4.17

4.18

4.18

4.17

4.16

4.16

4.17

4.17

4.19

4.19

4.20

4.20

4.19

4.13

4.13

4.17

4.19

4.18

4.17

4.17

4.22

4.22

4.23

4.23

4.19

4.10

4.14

0.0

0.0

0.0

8.8

98.9

228.0

183.6

133.6

36.6

36.6

36.0

36.0

36.4

36.9

36.8

36.3

36.3

35.4

353

35.2 -

35.1

35.5

38.1

38.1

36.2

35.5

35.9

36.6

36.3

34.1

34.1

33.5

33.4

35.6

39.9

65.1

234.0

234.0

114.8 i

l .

* These numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate i2.5 mm

I) Initial coordinate of fuel is 25.8 mm

2) End point coordinate orfuel is 166.8 mm

3) Free gas volume for coordinates 185-295 mm is presented in Table D.3

D-46
#B23T I of Rcfabricated Fuel Ros-

. i nedlddig - '|

9.4

E

._

0

U

9.3

9.2

9.1

_ l s,,, l l9,. ~,~-Li.....--r .Q 0

9.0

0 50 100

a)

150 200

Axial coordinate (mm)

250

b)

5

4

jut

_-~~~ fuel3 80

-rn

J

U

q

.E

3 Ir- - vvR I

-40 0

0

2 -

1 4 _ _ _ _ _ _ _ 4 4 -HIl

;....... . 0

.......... I............ ..... ... . ...

I, _ _ S l

0 50 100

c)

150 200

Axial coordinate, mm

4

250

Fig. D-10.1. (a) Results of Profilometry, (b) Radiography, (c) Axial Fuel Mass Distribution and Axial

Free Gas Volume Distribution for Fuel Rod #B23T

D47
iIiiiiiiIi11ii
E-1
Table E.1. Initial Characteristics Fresh Fuel Rods before IGR Reactor Tests. Representative values.

Characteristic Unit Value

1. Fuel (UO2)

1.1. Isotopic composition:

U235, U238 % by weight see Table E.2

u2 36 % by weight 0.023

U % by weight 0.057

1.2. Uranium impurity % by weight 0.152

1.3. Enrichment % see Table E.2

1.4. Oxygen coefficient per-unit not measured

1.5. Pellet outer diameter mm see Table E.2

1.6. Pellet inner diameter mm 2.2

1.7. Pellet height mm 9.8 - 13

1.8. Density gfcm3 10.5 - 10.6

1.9. Grain size not measured

1.10. Fuel shape, fuel macrostructure, see Fig. E.1

2. Cladding (Zr-i %Nb)

2.1. Composition:

Zr % by weight 98.75 - 98.95

Nb % by weight 0.9 - 1.1

0 % by weight < 0.1

N, C, Si, Al, Mo, Ni, Fe % by weight < 0.046

2.2. Cold work Autoclaving

2.3. Outer diameter, inner diameter mm. see Table E.2

2.4. Cladding microstructure , see Fig. E.1

3. Fuel rod

3.1. Fuel rod design see Fig. E.2

3.2. Fuel rod lengtht mm 300

3.3. Initial fill pressure MPa 2.0

3.4. Gas composition:

He % by volume 97.57

Impurity % by volume 2.43

3.5. Free volume cm3 see Table E.2

3.6. Fuel-cladding gap mm see Table E.2

E-2
Position I

Position2

Fig. E.1. Cross-Section Initial Appearance and Initial Cladding Microstructure by Polarized Light

and Fuel Microstructure for Fresh Fuel Rods

E-3
r

1. Lower cap

2. Fuel pellet

3. Cladding

4. Fixing ring

5. Upper plenum

6. Upper cap

Fuel pellet

6

5,'

4

3

2

I

L,, L2- individual values

for each fuel rod

* (see Table E.2)

Fig. E.2. Design Scheme of Fresh Fuel Rod

E-4
al idu- Characteristics of Refabricated Fuel Rods

| (Fresh fu jcladding)

Table E.2. Consolidated List of Characteristics for Fuel Rods ## H6C, B20C

Fuel rod number

Characteristic

H6C B20C

I.Fuel stack length (mm) 144 142

24 24

2. Coordinates of fuel stack (mm) 168 166

3.Fuel isotopic composition:

U2"5 (% weight) 4.47 4.46

U2"8 (% weight) 95.45 95.46

4.Total fuel mass (g) 62.59 59.19

5.U235 mass in fuel (g) 2.46 2.32

6.Uranium isotopes mass (g) 54.99 52.00

7.Enrichment (%) 4.47 4.46

8.L1 (see Fig. E.2) (mm) 144 142

9.L2 (see Fig. E.2) (mm) 113.1 115.1

l O.Total gas volume (cm3) 6.43 6.75

lI .Average inner diameter of cladding (mm) 7.754 7.750

12.Average outer diameter of cladding (mm) 9.154 9.146

13.Average thickness of cladding (mm) 0.700 0.698

14Average fuel pellet diameter (mm) 7.69 7.56

15.Average cladding-pellet gap (mm) 0.064 0.190

IE-5
Initial Individual Ciraicteristics of Refabricated Fuel Rods,

| (Frech fuel, Frehfi ,c~dfng)

Table E3. Free Gas Volume in Fresh Fuel Rods before IGR Reactor Tests for Axial Coordinates

185-295 mm.

Axial coordinate from lower Free gas volume

end of fuel rod (mm3)

(mm) 1-16C B20C

185 468 468

195 468 468

205 468 468

215 468 468

225 468 468

235 468 468

245 468 468

255 468 468

265 468 468

275 468 468

285 468 468

295 0 0

E-6
ir d #-I

E-7
Initial Individual Chaircteristics of Refabricated Fuel Rods

#H6C I (Freshfuel, Freshlt~adi~ng)- :-

Table E-1.1. Individual Initial Characteristics for Fuel Rod #H6C (measured)

Axial coordi- Cladding Cladding Cladding Fuel stack Fuel Linear Free gas

nate from inner thickness outer average mass fuel mass volume

lower end of diameter (mm) diameter diameter (g)* (g/cm)* (mm 3

)*3)

fuel rod (mm) (mm)4 ) (mm)*

(mm)

5

10

15

20

251)

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105.

110

115

120

125

130

135

140

145

150

155

160

165

1702)

175

180

7.757

7.757

7.757

7.757

7.756

7.755

7.754

7.754

7.753

7.752

7.751

7.750

7.749

7.749

7.749

7.749

7.750

7.751

7.752

7.753

7.754

7.755

7.756

7.757

7.758

7.759

7.759

7.759

7.759

7.759

0.697

0.697

0.698

0.700

0.700

0.700

0.700

0.701

0.701

0.701

0.701

0.702

0.703

0.704

0.705

0.705

0.701

0.701

0.701

0.700

0.700

0.700

0.698

0.698

0.697

0.696

0.696

0.697

0.696

0.697

9.151

9.151

9.153

9.157

9.156

9.155

9.154

9.156

9.155

9.154

9.153

9.154

9.155

9.157

9.159

9.159

9.152

9.153

9.154

9.153

9.154

9.155

9.152

9.153

9.152

9.151

9.151

9.153

9.151

9.153

0.0

0.0

0.0

0.0

7.65

7.65

7.65

7.64

7.64

7.68

7.69

7.69

7.69

7.69

7.69

7.69

7.70

7.70

7.70

7.70

7.70 -

7.69,

7.69

7.69

7.69

7.69

7.69

7.70

7.70

7.70

7.70

7.70

7.70

7.70

0.0

0.0

0.0

0.0

0.0

0.0

1.52

2.17

2.16

2.14

2.14

2.17

2.18

2.17

2.17

2.17

2.19

2.19

2.17

2.16

2.16

2.17

2.17

2.18

2.18

2.17

2.15

2.16

2.18

2.18

2.20

2.20

2.19

2.17

2.15

0.22

0.0

0.0

0.0

0.0

0.0

0.0

4.34

4.34

4.33

4.29

4.29

4.35

4.35

4.34

4.34

4.34

4.37

4.37

4.34

4.31

4.32

4.35

4.35

4.36

4.36

4.34

4.31

4.33

4.36

4.36

4.40

4.41

4.39

4.34

4.29

4.36

0.0

0.0

0.0

0.0

0.0

0.0

19.8

28.3

29.0

30.8

30.8

28.0

27.7

28.1

28.4

28.2

26.9

26.9

28.6

29.6

29.3

28.1

28.1

27.5

27.2

28.2

29.8

28.9

27.3

27.3

25.7

25.2

26.2

28.4

30.6

168.0

189.6

234.0

* These numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate ± 2.5 mm

I) Initial coordinate of fuel is 24 mm r

2) End point coordinate of fuel is 168 mm

Free gas volume for coordinates 15-295 mm is presented in Table E.3

) Cladding outer diameter is determined as the sum of the inner diameter and the width multiplied into 2

E-8
#H6C mInitial bd tilv Charcteristics of Refabricated Fuel Rods : - |

| (Fresh fu eili cladding) , . . -. : . . . I .|

9.4

L._

-c

0

*0

-II

_ I _ _ _ _ _ _ _ __ I_ _ _ _ _

931

9.2 -

9.1 -

9.0 -

fJel stack l~ngth U- 4 .- -

I 1 1 1- -t

1-

I I 4 4

0 50 100 150 200 250

a) Axial coordinate (mm)

c

c

(._ *0

r-C

C)

0.8 fuel stack length U - * _________________ - 4* -I

0.7 -t _ | £I

A

11 r. .

0 50 100 150 200 250

b) Axial coordinate (mm)

U

Z'-

I..

C

CA

C'

Xo

0

CI

0

0 50 100 150 200 250

c) Axial coordinate, mm

Fig. E-1.1. (a) Axial Distribution of Cladding Outer Diameter and (b) Cladding Thickness

(Profilometry), (c) Axial Fuel Mass Distribution and Axial Free Gas Volume Distribution

for Fuel Rod #H6C

E-9

A-PPEND

liuaI Chiaradcer

F * '4 5 - Amp TV ' .. . -, ..

. ;.'..'Lt-.'i''' .'.. ''/.'i ;' ' I ,; P - - -, ' - a, ' * ' * 'a,; -, if 4 , l

;: . .,: ,. . ,' . ,, . ' . . , . 1 . t A, -; . . ., fi s g ' . . ' l

uei.Ro-'#B2OO-.-.:.-..- i:- I I . . -; . TV, .......... -, - l K .1 ,. s ' i' ''' ' d . e S I ' + . b . i . l

.. . fi I, . , I,,- a.+; 4\ I',+ 'surly . .

E-1 I
#B20C Initial IndirviduakCtaracferistics of Rcefabricated Fuel Rods ;

' (Fresh' fuel, Frishi adlig) - -:: Rods. :: I

Table E-2.1. Individual Initial Characteristics for Fuel Rod NB20C (measured)

Axial coordi- Cladding Cladding Cladding Fuel stack Fuel Linear Free gas

nate from inner thickness outer average mass fuel mass volume

lower end of diameter diameter (mm) diameter ()* I(g/cm)* (mm3)*3)

fuel rod (mm) (mm) M ) (mm)*

(mm) 4 4

5

10

15

20

25')

30

35

40

45

50

55

60

65

70

75

80

85

90

95

100

105

110

115

120

125

130

135

140

145

150

155

160

1652)

170

175

180

7.752

7.753

7.754

7.755

7.756

7.757

7.757

7.755

7.754

7.752

7.751

7.749

7.749

7.747

7.748

7.748

7.748

7.748

7.749

7.748

7.749

7.747

7.747

7.747

7.747

7.746

7.744

7.743

7.743

0.701

0.701

0.699

0.700

0.699

0.700

0.700

0.702

0.700

0.700

0.701

0.702

0.703

0.702

0.701

0.700

0.699

0.698

0.696

0.696

0.694

0.694

0.694

0.692

0.693

0.693

0.693

0.691

0.691

9.154

9.155

9.152

9.155

9.154

9.157

9.157

9.159

9.154

9.152

9.153

9.153

9.155

9.151

9.150

9.148

9.146

9.144

9.141

9.140

9.137

9.135

9.135

9.131

9.133

9.132

9.130

9.125

9.125

0.0

0.0

0.0

0.0

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.57

7.57

7.57

7.57

7.57

7.57

7.57

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.56

7.57

7.57

7.57

0.0

0.0

0.0

0.0

0.0

0.0

0.0

1.45

2.07

2.08

2.10

2.10

2.09

2.09

2.09

2.10

2.10

2.11

2.11

2.09

2.09

2.07

2.05

2.06

2.09

2.09

2.08

2.08

2.08

2.08

2.08

2.08

2.08

2.07

2.06

1.44

0.0

0.0

0.0

0.0

0.0

0.0

0.0

4.15

4.15

4.17

4.20

4.20

4.18

4.18

4.19

4.20

4.20

4.22

4.22

4.18

4.17

4.14

4.10

4.12

4.18

4.18

4.17

4.17

4.17

4.17

4.17

4.15

4.15

4.14

4.11

4.13

0.0

0.0

0.0

0.0

0.0

0.0

0.0

26.3

37.5

36.5

34.8

34.8

35.9

35.9

35.5

35.1

34.9

34.2

34.2

36.1

36.3

38.0

39.5

38.7

35.9

35.9

36.5

36.5

36.5

36.4

36.5

37.3

37.3

38.1

39.2

82.0

183.6

209.8

234.0 I _ _ _ _J I__ _ _ _ _ _ 1 _ _ _ _ _

* These numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate ± 2.5 mm

1) Initial coordinate of fuel is 24 mm

2) End point coordinate orruel is 166 mm

) Free gas volume for coordinates 185-295 mm is presented in Table E.3

4) Cladding outer diameter is determined as the sum of the inner diameter and the width multiplied into 2

E-12
#B20C Inisial Indivadal Characteristics of Refabricated Fuel Rods:

(Fresh fiicl cladding) . - - - ;

9.4

9.3

c)

0

.E 9.1 *:

9.

9.0

II

II I

III

_I _ I I_ * _ _ I _ _ _ I___ _ _ _ _ _ _ _

100 150 200 250

a) Axial coordinatc (mm)

U

._

0

c5

.

U

*0

S.-

CS

U

U.9 -

fue stc =e= =

DI6I

I6 1 .SaC IW, ,

0 56 100 - 150 200 250

b) Axial coordinatc (mm)

5 50

4. - *4

II

fuel

............-------gas

'E

VI

C's

11.5 .1 4 4 4.-I-I 4. . .

-20

I ___....................e................-1 .. ,~~ .

n -1- -'[-1 to---l-------------'--'---

0

0 50 100 150 200 250

c) Axial coordinate (mm)

Fig. E-2.1. (a) Axial Distribution of Cladding Outer Diameter and (b) Cladding Thickness

(Profilometry), (c) Axial Fuel Mass Distribution and Axial Free Gas Volume Distribution

for Fuel Rod #B20C

E-13
-1, - -,-  -
F-I
t G _- ; t*B ~lr2 ... .... .Y~~~z~~a-22 : _ b. s.~~~~~~ 4 .:'.A.XA ............ \,-

Table F.1. Capsule Compositions and Pulse Half Width under IGR Tests

Type of fuel in

Number of fuel rods in capsule Number of Coolant 1, Pulse half refabricated

IGR test type width fuel rods:

Refabricated fuel rod Fresh fuel rod (s) - burup

HIT

H2T

H3T

H4T

H5T

H6T

H7T

H8T

-B9T

BIOT

BIT

B12T

B13T

H14T

HIST

H16T

H17T

H18T

B19T

B20T

B21T

B22T

B23T

H4C

HSC

H6C

H7C

H8C

B9C

BIOC

BIIC

B12C

B13C

H14C

HI5C

H16C

H17C

HI8C

B19C

B20C

B21C

B22C

B23C

103F-13

103F-14

103F-15

103F-8

103F-9

103F-7

103F-10

103F-5

103F-18

103F-16

103F-1 I

103F-19

103F-12

103F-I

103F-17

103F-3

103F-2

103F-23

103F-20

103F-6

103F-4

103F-22

103F-21

water

water

water

water

water

water

water

water

air

air

air .

air -

air

water

water

water

water

water

air

air

air

air

air

0.75

0.80

0.80

0.80

0.80

0.80

0.60

0.85

0.80

0.80

0.70

0.70

0.90

0.90

0.90

0.85

0.95

0.85

0.80

0.90

0.85

0.90

0.75

I

I

I

I

I

I

I

_________________________________ I _______________________ Z _

F-2
Table F.2.1. Reactor Power Shape Measured by Ionization Chamber and Energy Deposition as Pulse

Integration for Fuel Rods ##HIT, M1T, H3T, H4T

Fuel rod number

Time HIT H2T H3T H4T

(s) Power Energy Power Energy Power Energy Power Energy

(IA) I deposition (pA) deposition (pA) deposition (pA) deposition

. (pAs) _ (pAs) (pAs) (pAs)

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

8.5

9.0

9.5

0.00

5.48

20.79

29.59

44.78

69.86

99.46

96.19

60.98

36.42

22.70

15.04

10.54

7.77

5.96

4.74

3.87

3.24

2.76

2.40

2.10

1.80

1.50

0.75

0.00

0.00

2.37

13.67

18.63

25.94

37.24

54.27

74.80

90.48

100.01

105.80

109.50

112.03

113.84

115.20

116.26

117.12

117.83

118.43

118.94

119.39

119.78

120.11

120.67

120.86

0.00

2.43

13.83

20.51

31.29

49.26

79.32

123.24

142.67

100.84

60.18

35.14

21.10

13.23

8.69

5.95

4.24

3.12

2.37

1.85

1.54

1.32

1.10

0.55

0.00

0.00

1.21

7.64

11.03

16.13

24.04

36.66

56.78

84.52

109.23

125.09

134.40

139.90

143.26

145.42

146.86

147.87

148.60

149.14

149.56

149.89

150.18

150.42

150.83

150.97

0.00

3.35

10.84

14.51

21.10

34.02

59.78

105.42

159.29

173.25

121.78

72.37

42.20

25.36

15.95

.10.50

7.23

5.17

3.83

2.92

2.32

1.80

1.29

0.00

0.00

1.68

8.18

10.69

14.18

19.56

28.67

44.87

71.51

105.85

135.78

154.90

166.09

172.69

176.74

179.34

181.08

182.31

183.20

183.87

184.39

184.80

185.11

185.43

0.00

1.47

3.58

4.34

5.52

7.55

11.37

19.03

34.25

59.62

82.21

74.54

48.38

26.82

14.79

8.86

5.93

4.39

3.54

3.02

2.68

2.43

2.22

1.71

1.13

0.55

0.00

0.00

0.69

3.12

3.90

4.88

6.17

8.02

10.98

16.15

25.41

39.87

56.05

68.41

75.77

79.80

82.10

83.55

84.57

85.35

86.01

86.58

87.09

87.55

88.53

89.24

89.66

89.82

.3. & A. a _____________ .i.

F-3
Table F.2.2. Reactor Power Shape Measured by Ionization Chamber and Energy Deposition as Pulse

Integration for Fuel Rods ##H5T, H16T, H17T, H8T

Fuel rod number

Time H-5T 1-6T H7T 1-8T

(s) Power Energy Power I Energy Power I Energy Power Energy

(tLA) deposition (giA) deposition (ptA) deposition (ptA) deposition

__ _ _ _ _ _ (jAs) __ _ _j (pAs) __ _ j _ , (pAs) __ _ _ (pAs)

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

8.5

9.0

9.5

0.00

1.60

9.92

13.98

19.83

28.46

41.50

61.23

87.66

97.72

63.03

35.35

20.39

12.54

8.22

5.71

4.16

3.16

2.48

2.01

1.66

1.40

1.20

0.80

0.40

0.00

0.00

0.70

5.38

7.74

11.09

15.87

22.78

32.93

47.76

67.06

83.30

92.90

98.32

101.54

103.58

104.95

105.93

106.65

107.21

107.66

108.02

108.33

108.59

109.09

109.39

109.49

0.00

1.00

1.99

2.23

2.53

2.94

3.59

4.72

6.84

11.04

19.40

34.24

52.96

62.40

48.76

28.70

15.84

9.16

5.79

4.01

3.02,

2.42

2.03

1.50

1.17

0.78

0.39

0.00

0.00

0.50

1.99

2.41

2.89

3.43

4.08

4.90

6.03

7.77

10.73

15.99

24.72

36.53

47.98

55.65

59.98

62.41

63.87

64.83

65.53

66.06

66.51

67.37

68.04

68.53

68.82

68.92

0.00

2.46

8.11

10.28

13.48

18.90o

29.32

51.42

95.81

137.82

96.40

36.93

12.09

5.00

2.91

2.23

1.98

1.75

1.51

1.28

1.05

0.81

0.58

0.00

0.00

1.23

5.89

7.72

10.08

13.26

17.97

25.78

40.11

64.30

88.84

101.71

106.16

107.73

10 8.49

108.99

109.41

-109.78

110.11

110.39

110.62

110.80

110.94

-111.09

0.00

0.55

1.09

1.22

1.35

1.50

1.68

1.94

2.35

3.02

4.24

6.63

11.49

20.87

34.25

39.42

32.66

21.74

12.71

7.23

4.32

2.81

2.01

1.20

0.90

0.68

0.45

0.23

0.00

0.00

0.27

1.09

1.32

1.58

1.87

2.18

2.54

2.97

3.50

4.21

5.28

7.03

10.18

15.69

23.32

30.65

36.09

39.49

41.43

42.55

43.25

43.73

44.49

45.00

45.40

45.68

45.85

45.91

F-4
'iRacr s Chr-trc 2 . .s 

Table F.23. Reactor Power Shape Measured by Ionization Chamber and Energy Deposition as Pulse

Integration for Fuel Rods ##B9T, BlOT, B1lT, B12T

Fuel rod number

Time B9T BIOT J BlIT B12T

(s) Power Energy Power Energy Power Energy Power Energy

(pA) deposition (gA) deposition (pA) deposition ("A) deposition

(ILAs) (pAs) . (pAs) (plAs)

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

8.5

9.0

9.5

0.00

2.37

12.25

16.79

23.48

34.18

53.03

86.33

93.63

66.99

43.05

27.28

17.66

11.81

8.19

5.87

4.34

3.30

2.58

2.06

1.67

1.30

0.93

0.00

0.00

1.06

7.24

10.12

14.10

19.78

28.33

42.03

61.14

77.31

88.18

95.10

99.52

102.42

104.39

105.78

106.80

107.55

108.14

108.60

108.97

109.27

109.49

109.72

0.00

1.82

5.16

7.49

12.33

22.60

41.96

65.66

71.98

52.10

32.73

20.42

13.17

8.88

6.25

4.57

3.46

2.70

2.16

1.77

1.48

1.26

1.08

0.54

0.00

0.00

0.91

3.99

5.23

7.15

10.53

16.83

27.66

41.89

54.46

62.84

68.05

71.35

73.52

75.02

76.09

76.88

77.49

77.98,

78.37

78.69

78.97

79.20

79.60

79.74

0.00

2.70

13.81

19.24

27.36

40.19

61.77

99.64

152.17

128.31

75.41

43.39

26.36

17.10

11.77

8.53

6.46

5.06

4.08

3.38

2.85

2.45

2.14

1.43

0.71

0.00

0.00

1.21

8.08

11.36

15.96

22.62

32.63

48.45

73.71

103.35

123.46

135.03

141.84

146.10

148.95

150.95

152.44

153.58

154.49

155.23

155.85

156.38

156.84

157.74

158.27

158.45

0.00

2.20

17.05

25.17

38.42

62.31

105.92

115.23

78.67

48.08

29.20

18.27

11.91

8.09

5.71

4.18

3.15

2.44

1.94

1.57

1.28

1.00

0.71

0.00

0.00

0.91

8.46

12.63

18.88

28.72

45.21

68.86

88.34

100.82

108.39

113.05

116.01

117.98

119.35

120.32

121.05

121.61

122.04

122.39

122.67

122.90

123.07

123.25

£ .J. I I .. I

F-5
IGR~eato ;stils >o I

Table F.2.4. Reactor Power Shape Measured by Ionization Chamber and Energy Deposition as Pulse

Integration Fuel Rods #NB13T, HU4T, H1ST, H16T

Fuel rod number

Time B13T H14T HIST | H16T

(s) Power Energy Power Energy Power Energy Power Energy

(plA) deposition (pA) deposition (pA) deposition (pA) deposition

- (jxAs) (jiAs) (.LAs) (pAs)

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

8.5

9.0

9.5

0.00

3.15

17.70

27.92

45.72

76.65

126.47

184.71

192.94

155.05

98.38

53.04

27.63

15.57

10.05

7.47

6.22

5.62

5.17

4.72

4.27

3.82

3.37

2.25

1.12

0.00

- 0.00

1.57

9.46

13.93

21.14

33.12

53.12

84.42

123.27

158.61

183.97

198.80

206.59

210.76

213.26

214.98

216.34

217.51

218.59

219.58

220.48

221.29

222.01

223.42

224.26

224.54

0.00

0.43

0.88

1.02

1.26

1.68

2.48

4.07

7.14

11.95

15.84

14.83

10.84

6.85

4.11

2.51

1.63

1.12

0.83

0.64

0.52

0.43

0.37

0.24

0.12

0.00

0.00

0.21

0.86

1.05

1.28

1.57

1.97

2.61

3.70

5.59

8.43

11.56

14.15

15.91

16.98

17.63

18.03

18.31

18.50

18.64

18.76

18.86

18.94

19.09

19.18

19.21

0.00

1.71

7.65

12.73

23.01

40.08

54.42

49.78

36.20

24.53

16.50

11.30

7.95

5.75

4.29

3.28

2.56

2.05

1.67

1.38

1.17

0.99

0.86

0.43

0.00

0.00

0.71

4.40

6.38

9.85

16.07

25.72

36.44

'45.05

51.07

55.12

57.86

59.76

61.12

62.11

62.86

63.44

63.90

64.27

64.58

64.83

65.05

65.23

65.55

65.66

0.00

0.41

0.82

0.90

0.98

1.06

1.14

1.22

1.31

1.39

1.48

1.67

2.02

2.71

4.09

6.94

12.57

21.85

31.57

34.04

26.08

15.99

9.22

3.10

1.71

1.16

0.78

0.52

0.26

0.00

0.00

0.20

0.82

0.99

1.18

1.38

1.60

1.84

2.09

2.36

2.65

2.96

3.32

3.79

4.45

5.52

7.42

10.81

16.20

22.93

29.06

33.23

35.69

38.38

39.52

40.22

40.71.

41.03

41.23

41.29

F-6
1GR Racim Characteristics

Table F.2.5. Reactor Power Shape Measured by Ionization Chamber and Energy Deposition as Pulse

Integration for Fuel Rods ##uI17T, H18T, B19T, B20T

Fuel rod number

Time H17T H18T B19T B20T

(s) Power Energy Power Energy Power Energy Power Energy

(tA) deposition (pA) deposition (11A) deposition (VA) deposition

(ptAs) (pAs) (ptAs) (VAs)

0.0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

1.0 0.20 0.07 1.16 0.58 1.93 0.97 0.52 0.26

2.0 0.60 0.47 2.68 2.35 5.05 4.02 1.05 1.05

2.2 0.67 0.60 3.79 2.99 8.11 5.29 1.15 1.27

2.4 0.75 0.74 6.35 3.97 15.90 7.58 1.25 1.51

2.6 0.83 0.90 12.29 5.76 33.62 12.35 1.36 1.77

2.8 0.94 1.07 24.05 9.30 57.64 21.53 1.46 2.05

3.0 1.08 1.27 38.56 15.59 64.13 34.15 1.64 2.36

3.2 1.29 1.51 44.82 24.13 48.03 45.52 1.93 2.71

3.4 1.66 1.80 36.42 32.44 31.20 53.36 2.42 , 3.14

3.6 2.32 2.19 24.37 38.48 19.88 58.39 3.30 3.71

3.8 3.53 2.76 15.70 42.43 12.96 61.62 5.02 4.52

4.0 5.85 3.68 10.28 44.99 8.75 63.75 8.44 5.83

4.2 10.18 5.24 6.96 46.69 6.14 65.23 15.13 8.12

4.4 16.97 7.93 4.89 47.86 4.47 66.27 26.30 12.20

4.6 23.53 12.03 3.56 48.69 3.35 67.05 38.56 18.74

4.8 23.92 16.89 2.68 49.31 2.59 67.64 41.92 27.00

5.0 18.79 21.22 2.07 49.78 2.05 68.10 32.41 34.57

5.2 12.16 24.30 1.64 50.15 1.66 68.47 20.03 39.78

5.4 7.16 26.20 1.33 50.45 1.37 68.77 11.46 42.86

5.6 4.23 27.31 1.10 50.69 1.15 69.03 6.73 44.63

5.8 2.66 27.99 0.93 50.89 0.98 69.24 4.26 45.71

6.0 1.81 28.42 0.79 51.06 0.85 69.42 2.95 46.42

6.5 0.93 29.07 0.40 51.36 0.57 69.78 1.60 47.49

7.0 0.55 29.43 0.00 51.46 0.28 69.99 1.11 48.15

7.5 0.27 29.64 - - 0.00 70.06 0.78 48.62

8.0 0.07 29.72 - - 0.51 48.94

8.5 0.00 29.73 0.26 49.14

9;0 - - 0.00 49.20

9.5 - - U & .8. .8. 1 & .5.

F-7
IGR Reactor Tests edstics

Table F.2.6. Reactor Power Shape Measured by Ionization Chamber and Energy Deposition as Pulse

Integration for Fuel Rods #HB21T, B22T, B23T

Fuel rod number

Time B21T B22T B23T

(s) Power Energy Power Energy Power Energy

(IiA) deposition (pA) deposition (pjA) deposition

(pAs) I (jiAs) (pAs)

0.0

I 1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

*5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

8.5

9.0

9.5

0.00

0.44

0.89

0.98

1.06

1.15

1.31

1.63

2.27

3.61

6.44

11.95

20.38

28.52

31.62

25.80

17.18

10.87

6.92

4.54

3.08

2.16

1.57

0.80

0.50

0.25

0.00

0.00

0.22

0.89

1.07

1.28

1.50

1.74

2.03

2.41

2.99

3.96

5.75

8.95

13.88

20.00

25.87

30.15

32.91

34.66

35.79

36.54

37.06

37.43

37.99

38.30

38.49

38.55

0.00

0.60

1.56

2.13

3.20

5.44

10.26

19.24

26.46

23.93

18.70

13.40

9.14

6.08

4.01

2.64

1.75

1.17

0.79

0.55

0.38

0.27

0.19

0.00

0.00

0.30

1.27

1.63

2.15

2.99

4.50

7.39

12.12

17.23

21.51

24.71

26.95

28.45

29.45

30.10

30.53

30.82

31.02

31.15

31.24

31.31

31.35

31.40

0.00

1.68

5.15

7.00

10.56

18.09

34.40

64.21

92.29

80.54

52.37

32.41

20.56

13.63

9.46

6.85

5.14

3.99

3.18

2.60

2.17

1.84

1.58

0.79

0.00

0.00

0.84

3;95

5.15

6.87

9.64

14.70

24.37

40.36

58.33

71.55

79.88

85.08

88.44

90.72

92.33

93.52

94.42

95.14

95.71

96.19

96.59

96.93

97.52

97.72

I

£ I I .J. .L

F-8
CGR Reaharateristics 1: - : ; -- : |

C)

0.

0

-.

C)

94)

#H1T

power

120- .. .. cnergy - - -120

deposition .... .

Ad YOon

"IN

ITV

Ion 6:n

3

V- -.- 30

A I r - 3

CA2

0

Un

0

0.

10

C)

L-.

0

C.)

Cl

- I

0 2 4 6

v

8 10

Time (s)

=L. C)

0

0.

I0

W.)

C)

Cn

=LC

.0

17

00.

C)

0

Ml

I-.

0

0

C)

0 2 4 6 8 10

Time (s)

Fig. F.1. Reactor Power Shape and Energy Deposition for Fuel Rods ##HMT, H2T Tests

F-9
IGR Reactor eristics

250

. #143T

power

. 'd energy

deposition

I

I-.

0

L.

0

es

4)

200 -

150 -

I-i 4 4

I

.O.......... .....-----

_ I- -1 t -I-

-250

-200 _

cn

0

-150 :C

0000

- 100

0

-50

100

I1D

50

0

4 4 -- 4 4-

BY9

I

_ _e _ _ I

_- i _ _________

0 2 4 6 8 10

Time (S)

150

0

0.

L.

U

U3

120

90

0

0

0. U

0.

0

la

0

0

U3

60

30

0

Time (s)

Fig. F.2.. Reactor Power Shape and Energy Deposition for Fuel Rods ##H3T, H4T Tests

F-10
of 120

=L. C)

0

X. 90

L. 0

Cs

C)

]iGRRcck e Characteristics

150

ST

-. ,-120

00

90 =0

-30

6 8 10

Time (s)

. -150

ST)

-12

66 .

.*-0 0

...... ................... ......... ... 6 >

60n

0 2 4

150

=L

C)

0

a-1

0

C).

120

90

60

30

0

.'

0 2 4 6 8 10

Time (s)

Fig. F.3. Reactor Power Shape and Energy Deposition for Fuel Rods ##H5T, H6T Tests

F-il
I|R IRector TestM$7tcristics ; -|

150

- 120

0

°. 90 Ic.)

U

60

3060

0.

U

v.

U

0

I..

U

Cl

Uo

0 2 4 6 8 10

Time (s)

50 50

I-1

0

0.

2-.

0

4-.

40 =n

Cl 0

30 ..

0

0.

U

20 c

C

0

4-

U

C0

10 W

0 2 4 6 8 . 10

Time (s)

Fig. F.4. Reactor Power Shape and Energy Deposition for Fuel Rods 0#117T, 118T Tests

F-12
IR ci Characteristics |

MA

I

IS.

0

;I0

C.

0

#B9T-1U

120 . . ....... -120

90 _ ____ _ -90

60 60

30 -30

0 -* * * _ _ _1- I__ 

0

0

0C

la

0

1-

0

C-)

0 2 4 6 8 10

Time (s)

150

0

0.

4-

U

C3

9U

120

90

in

0

0

0.

0

U

0

S.-

0

U

C2

* v 60

30

0

Time (s)

Fig. F.5. Reactor Power Shape and Energy Deposition for Fuel Rods ##B9T, BIOT Tests

F-13
IGR ReaictorTtc rstics -:: -;:,k

C.)

0

:11

0

I..

0

250

200

150

100

50

0

Time (S)

cn

0

C.

C.)

Cn

c

0

0.

C)

0

C)

c)

I._

ID

0

4o

S;

c)

To0

To

0.4

=L.

0

S.

C)

Time (s)

Fig. F.6. Reactor Power Shape and Energy Deposition for Fuel Rods ##B11T, B12T Tests

F-14
U-.

L.

0

L. U-.0

C.)

C)

IGR Characteristics -.-

250

13T

. ..................

-200

power 150 :,

0

. ............. energy

deposition

-100

0

. . i

_ t C) 

Time (s)

50 .7 *

#H14T

e.......

power

energy

deposition

I

50

0.

P-.

40 - I

A(I - 4 4 4

20

*10

A

..................

-TV,

o

Ca

-30 co0

Ca

- 20 c

C.)

U.

1 0 0

- 0

I;.'

A

I,L -m .L

0 2 4 6 8 10

Time (s)

Fig. F.7. Reactor Power Shape and Energy Deposition for Fuel Rods ##B13T, H14T Tests

F-15
I..

0

:.

L.

0

*0

L.

U

*|IGRReactorTsific - |

115T -150

-120

0

-90 W0

0.

.............. ........... .3 ,. -60 :°

00

_ _ _ _ _ _ _ _.2A 9

Time (s)

50

L..

0

0

S.

U2

40

30

I #1116T

power

_ . .......... energy .. ....... ............ 

deposition

_A_. I .

I!'IA

20

10

0

-

50

40 I

0

=L

.0

0.

20

0

Q.

10 A

0o

I .1 _____________________________ I.....___

0 2 4 6 8 10

Time'(s)

Fig. F.8. Reactor Power Shape and Energy Deposition for Fuel Rods #II15T, H16T Tests

F-16
IGR Characteristics' -, .

50 50

I0

0.

U

es

go

40

30

0

0

10

U

20

10

Time (s)

150 -150

.1 oA

I-1

0

U03

120

90

60

30

0

90 4-En

0

00

0

60 2

r0

S30 J

0

Time (s)

Fig. F.9. Reactor Power Shape and Energy Deposition for Fuel Rods ##II17T, H18T Tests

F-17
|R Reactor TestX 3estics

150

L

0

0

C's

C)

Cn

0

0

0

la

>I

0

C)

C) PU

Time (s)

50 50

*An

0

0

L.

C)

40

30

20

10

0

(12

30 *e,

'n

0=

C)

.0.

C)

0*

0)

10 X

00

Time (s)

Fig. F.10. Reactor Power Shape and Energy Deposition for Fuel Rods #f#B19T, B20T Tests

F-18
I 1i Ch - t er:s Ira ti ; 'r 

IGR R i -CharacterisU6c ' :, I -::-:

C)

0

a0

S)

C)3

50

40

30

50

40 1-1 0

4-1

C

*30

0.

U

C) .0

10 C

0

20

10

0

0 2 4 6 8 10

Time (s)

Ic)

0

0-a.

0

U2

C)

50-

40 -

30-

I #B22T

power

_ ....... energy

deposition

. ...............

-50

A fA _ l l

20

10

"U

0IQ

30

00

0.

20 X

a- 0

U

C)

10 C4

0

-4. -I- -4--

_ _ I |

( I4 )I I _ _

0 2 4 6 8 10

Time (s)

Fig. F.11. Reactor Power Shape and Energy Deposition for Fuel Rods ##B21T, B22T Tests

F-19
|IGR Reactor Tet cimstics :

1~

4-.

0

U I._

0

la

EP

O

el

Time (s)

Fig. F.12. Reactor Power Shape and Energy Deposition for Fuel Rod #B23T Test

F-20
1taurn

eariat~

radia";tei

ridCacul-at ed-

,adig dui

F.ii: fteiscs 'of~

ted U e!,,*- P -rei-,r

!fter• IGRTests

Ifidividuald 4 rcteristics or F lT 'under IGRL, Test

G-1
#H1T IndividUal Charaictcin&&vDfRefabricated Fuel Rods

I(Preirradiated Fuej-• diated Cladding) under IORTests

C

Axial coordinate (mm)

Fig. G-I.1. Appearance of Fuel Rod #H1T (photographs and X-ray photograph) and Profilometry

G-2
#H1T indivMiduallifcristics of Refabricated Fuel Rods' -

I(Preirradijit'0el. Preirradiated Cladding) under IGR Tests

Position I

Position 1 Position 2

- '• *t * * b .a " g '.4 P "1) .t * "

" - . -r . * r Z '. , 1. . .

" '. [

-- ,-,. 10 Am~

Fig. G-1.2. Cross-Section and Cladding Microstructure for Fuel Rod #11T at 90 mm Elevation

G-3
#H1T I ~lndivrd~i~Z~T Refab~aie~l Fuel Rods

~eirrIdia. e.~ ~ Qa~lding) uz~dcr IOR Tests:.:1

0

I

Position I Position 2

Fig. G-1.3. Fuel Microstructure of Fuel Rod MHIT at 90 mm Elevation

G4
#HIT ]ndividu ___ cteristicsofRefabricat~d Fuel Rods Tests ,(Preiffad'iý ,'4 Pre'irradiated Claddin-g) 'under IGR T est ".:I

Table G-1.1. Time Dependent Energy Characteristics of Fuel Rod #1i1T

Reac- Cumulative number of fissions Power Energy

tor in fuel rod (fiss) of fuel deposition

Time energy rod in fuel rod

(s) deposi- U235 U238 

pu

239 pu241 Other Total (kW) cal/g J/g fuel

tion') x10-14 xI0"13 xl0 14 xl0"14 isop xl0"14 fuel

(%) topes xlO-11

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

9.0

10.0

20.0

30.0

00

0.000

1.890

10.90

14.90

20.70

29.80

43.40

59.80

72.30

80.00

84.60

87.60

89.60

91.00

92.10

92.90

93.60

94.20

94.70

95.10

95.40

95.70

96.00

96.40

96.80

97.00

97.30

97.60

97.90

99.20

99.60

100.0

0.000

0.128

0.742

1.010

1.410

2.020

2.940

4.060

4.910

5.430

5.740

5.940

6.080

6.170

6.250

6.310

6.350

6.390

6.420

6.450

6.470

6.490

6.510

6.540

6.570

6.580

6.600

6.620

6.640

.6.730

6.760

6.810

0.000

0.032

0.184

0.251

0.349

0.502

0.731

1.010

1.220

1.350

1.430

1.480

1.510

1.530

1.550

1.570

1.580

1.590

1.600

1.600

1.610

1.610

1.620

1.620

1.630

1.640

1.640

1.640

1.650

1.670

1.680

1.690

0.000

0.197

1.140

1.550

2.160

3.100

4.510

6.220

7.520

8.320

8.800

9.110

9.320

9.460

9.580

9.670

9.740

9.800

9.850

9.890

9.920

9.950

9.980

10.00

10.10

10.10

10.10

10.20

10.20

10.30

10.40

10.40

0.000

0.081

0.469

0.639

0.890

1.280

1.860

2.560

3.100

3.430

3.630

3.760

3.840

3.900

3.950

3.990

4.020

4.040

4.060

4.080

4.090

4.110

4.120

4.140

4.150

4.160

4.170

4.190

4.200

4.250

4.270

4.310

0.000

0.155

0.898

1.220

1.700

2.450

3.570

4.910

5.940

6.570

6.950

7.190

7.360

7.480

7.570

7.640

7.690

7.740

7.780

0.000

0.410

2.370

3.230

4.490

6.450

9.390

12.90

15.70

17.30

18.30

19.00

19.40

19.70

19.90

20.10

20.30

20.40

20.50

20.60

20.70

20.70

20.80

20.90

21.00

21.00

21.10

21.10

21.20

21.50

21.60

21.70

0.000

2.720

10.30

14.70

22.20

34.70

49.40

47.80

30.40

18.20

11.40

7.620

5.390

4.010

3.100

2.490

2.050

1.730

1.490

1.260

1.070

0.917

0.794

0.581

0.451

0.368

0.313

0.269

0.216

0.056

0.030

0.000

0.000

4.630

26.70

36.50

50.80

72.90

106.0

146.0

177.0

196.0

207.0

215.0

220.0

223.0

226.0

228.0

230.0

232.0

233.0

234.01

235.0

236.0

236.0

238.0

239.0

240.0

240.0

241.0

242.0

246.0

248.0

253.0

0.000

19.40

112.0

153.0

213.0

305.0

444.0

611.0

741.0

820.0

867.0

900.0

921.0

933.0

946.0

954.0

963.0

971.0

975.0

980.0

984.0

988.0

988.0

996.0

1000.

1005.

1005.

1009.

1013.

1030.

1038.

1059.

7.810

7.840

7.860

7.880

7.920

7.950

7.970

7.990

8.020

8.050

8.150

8.180

8.250

Maximum value of power is 52.5 kW (t - 2.90 s).

1) Current energy deposition per maximum energy deposition (at infinite time)

G-5

. ---
#H1T Individual CharactensticjofRefabricated Fuel R6ds

(Preirradiated Fue.•iNfiridiated Cladding) under IGR Tests

Table G-1.2. Axial Energy Characteristics of Fuel Rod #H1T

Axial Cumulative number of fissions Maxi- Energy deposition

coordi- at axial interval (fiss) mum at infinite time*

nate powerof

from u23 U"' Pu239 Pu24' Other Total fuel rod cal/g J/g perlower ox10"3 x-10"1 xI-013 x 10"13 iso- x10"13 (kW) fuel fuel unit3

) end of tpst-.0

fuel rod 0tapes t2.90s

(mm) xI0"lj

10.0

15.0

0.000 1 0.000

0.000 0.000

20.0')

25.0

30.0

35.0

40.0

45.0

50.0

55.0

60.0

65.0

70.0

75.0

80.0

85.0

90.0

95.0

100.0

105.0

110.0

115.0

120.0

125.0

130.0

135.0

140.0

145.0

150.0

155.0

160.0

165.0

170.0

175.0

180.02)

185.0

0.338

1.690

1.690

1.690

1.690

1.690

2.380

2.370

2.340

2.330

2.320

2.390

2.440

2.410

2.360

2.360

2.360

2.320

2.280

2.240

2.230

2.170

2.130

2.090

2.050

2.130

2.190

2.180

2.170

2.220

2.270

2.180

0.423

0.000

0.717

3.590

3.590

3.590

3.590

3.590

5.690

5.700

5.710

5.720

5.720

5.690

5.660

5.680

5.700

5.700

5.700

5.720

5.740

5.760

5.760

5.790

5.810

5.820

5.840

5.810

5.780

5.780

5.790

5.770

5.740

5.780

1.160

0.000

0.000

0.000

0.524

2.620

2.620

2.620

2.620

2.620

3.490

3.490

3.490

3.480

3.480

3.500

3.510

3.500

3.490

3.490

3.490

3.480

3.470

3.460

3.460

3.440

3.430

3.420

3.410

3.430

3.450

3.440

3.440

3.450

3.470

3A40

0.686

0.000

0.000

0.000

0.217

1.090

1.090

1.090

1.090

1.090

1.420

1.430

1.430

1.430

1.430

1.420

1.420

1.420

1.430

1.430

1.430

1.430

1.430

1.430

1.430

1.430

1.430

1.430

1.430

1.430

1.430

1.430

1.430

1.430

1.430

1.430

0.286

0.000

0.000

0.000

0.369

1.850

1.850

1.850

1.850

1.850

2.750

2.760

2.760

2.770

2.770

2.750

2.740

2.750

2.760

2.760

2.760

2.770

2.780

2.790

2.790

2.810

2.820

2.820

2.830

2.820

2.800

2.800

2.810

2.790

2.780

2.800

0.564

0.000

0.000

0.000

1.090

5.440

5.440

5.440

5.440

5.440

7.360

7.340

7.310

7.300

7.280

7.380

7.440

7.390

7.330

7.330

7.330

7.280

7.240

7.190

7.180

7.100

7.050

7.010

6.960

7.050

7.130

7.110

7.100

7.160

7.220

7.110

1.410

0.000

0.000

0.000

0.263

1.310

1.310

1.310

1.310

1.310

1.780

1.780

1.770

1.760

1.760

1.780

1.800

1.790

1.770

1.770

1.770

1.760

1.750

1.740

1.730

1.720

1.710

1.690

1.680

1.710

1.720

1.720

1.720

1.730

1.750

1.720

0.340

0.000

0.000

0.000

279.0

279.0

279.0

279.0

279.0

279.0

261.0

260.0

257.0

256.0

251.0

253.0

254.0

251.0

247.0

249.0

253.0

252.0

250.0

249.0

249.0

243.0

244.0

244.0

241.0

243.0

246.0

244.0

243.0

248.0

250.0

254.0

236.0

0.000

0.000

0.000

1168.

1168.

1168.

1168.

1168.

1168.

1093.

1088.

'1076.

1072.

1051.

1059.

1063.

1051.

1034.

1042.

1059.

1055.

1047.

1042.

1042.

1017.

1021.

1021.

1009.

1017.

1030.

1021.

1017.

1038.

1047.

1063.

988.0

0.000

0.00

0.00

1.00

1.00

1.00

1.00

1.00

1.00

0.94

0.93

0.92

0.92

0.90

0.91

0.91

0.90

0.89

0.89

0.91

0.90

0.90

0.89

0.89

0.87

0.87

0.87

0.86

0.87

0.88

0.87

0.87

0.89

0.90

0.91

0.85

0.00

All numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate + 2.5 mm

1) Initial coordinate of fuel is 21.5 mm

2) End coordinate of fuel is 178.5 nun

3) Current value per maximum value

G-6
#HIT I Individualdcteristics of Refabricated Fuel Rods',I

I (Preirradia aFiell Preirradiated Cladding) under IGR Tests.

Table G-1.3. Radial Energy Characteristics of Fuel Rod #H1T

Coordinates of fuel zones (mm)

Characteristics* I zone 2 zone 3 zone 4 zone

1.2 -2.811 2.811-3.432 3.432-3.704 3.704-3.790

Number of fissions x 10-i 4 (fiss) 3.020 -1.770 0.867 0.282

Power of fuel rodi) (kW) 7.150 4.190 2.050 0.668

U235 Energy deposition2) (cal/g fuel) 78.20 76.40 74.80 73.00

Energy deposition2 ) (J/g fuel) 327.0 320.0 313.0 306.0

Energy deposition3) (per-unit) 1.000 0.977 0.957 0.934

Number of fissions x 10-12 (fiss) 7.940 4.470 2.060 0.622

Power of fuel rodt) (kW) 0.186 0.105 0.048 0.014

U238 Energy deposition2 ) (cal/g fuel) 2.020 1.900 1.750 1.580

Energy deposition2 ) (J/g fuel) 8.460 7.950 7.330 6.610

Energy deposition3) (per-unit) 1.000 0.941 0.866 0.782

Number of fissions x 10-" (fiss) 3.770 2.560 1.760 0.993

Power of fuel rod') (kW) 9.240 6.280 4.300 2.430

Pu 239 Energy deposition2 ) (cal/g fuel) 101.0 114.0 157.0 266.0

Energy deposition2 ) (J/g fuel) 423.0 477.0 657.0 1113.

Energy deposition3) (per-unit) 0.380 0.429 0.590 1.000

Number of fissions x104 3 (fiss) 14.90 10.50 7.560 4.500

Power of fuel rod') (kW) 3.570 2.530 1.820 1.080

Pu2 41 Energy deposition2) (cal/g fuel) 39.10 46.20 66.30 118.0

Energy deposition') (J/g fuel) 164.0 193.0 278.0 494.0

Energy deposition3

) (per-unit) 0.331 0.392 0.562 1.000

Number of fissions xlI" t (fiss) 3.400 2.090 1.220 0.581

Other Power of fuel rod') (kW) 0.008 0.005 0.003 0.001

isoto- Energy deposition2 ) (cal/g fuel) 0.090 0.092 0.107 0.154

pes Energy deposition2 ) (J/g fuel) 0.380 0.390 0.450 0.640

Energy deposition3) (per-unit) 0.583 0.599 0.695 1.000

Number of fissions xI0"-4 (fiss) 8.340 5.430 3.400 1.740

Power of fuel rod') (kW) 20.20 13.10 8.240 4.210'

Total Energy deposition2 ) (cal/g fuel) 220.0 239.0 300.0 459.0

Energy deposition2) (J/g fuel) 921.0 1000. 1256. 1921.

Energy deposition3 ) (per-unit) 0.479 0.521 0.654 1.000

1) at time of 2.90 s. 2) at infinite time. 3) Current value per maximum value.

* All numerical values of characteristics were calculated for undamaged part of fuel stack only (See Table C.2.1.)

G-7
#HIT Individual ChameaRc sti-ofl~efabricated Fuel Rods,

:(Preir'radiated Futp, 1'Wiradiaied Cladding) under IGR Tests

Table G-1.4. Fuel Enthalpy Vs. Time Calculated by FRAP-T6 Code for Fuel Rod #111T

Enthalpy at fuel radius F 1) Energy deposition Time (cal/, fuel) Fuel enthalpy I in fuel rod

(s) 1.20mm 2-_2 mm1 3.47 mm 13.79 mm calg fuel IJg fuel calg fuel J/g fuel

0.0

1.0

2.0

22

2.4

2.6

2.8

3.0

32

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

5.28

27.5

34.5

47.6

67.6

97.7

140

163

179

188

191

192

192

191

189

186

183

179

175

171

167

163

149

138

123

114

80.7

13.1

0.00

5.19

25.9

32.2

43.9

61.9

88.1

124

141

150

153

152

150

148

145

142

138

135

132

128

124

118

113

102

95.7

87.9

83.3

65.2

12.6,

0.00

4.92

22.5

27.1

36.2

45.6

62.2

83.7

94.0

102

106

108

107

106

104

101

99.7

98.3

95.7

89.9

83.3

78.5

75.7

71.1

68.8

65.7

63.7

54.1

12.2

0.00

4.55

18.5

21.6

27.5

26.7

34.7

42.2

56.3

71.0

79.5

82.4

82.9

82.2

81.2

80.0

80.0

79.6

74.9

66.6

60.2

58.2

57.6

56.8

56.3

55.2

54.3

48.3

11.9

0.00

5.13

25.2

31.2

42.4

57.9

82.1

115

132

144

149

150

150

148

146

144

141

138

135

,131

126

121

117

107

100

91.8

86.6

66.5

12.6

0.00

21.5

106

131

178

243

344

482

555

603

624

630

.629

622

614

603

591

580

566

547

527

507

490

448

421

385

363

279

52.9

0.00

5.19

28.0

35.4

49.1

70.3

102

148

176

196

208

215

220

224

226

229

230

232

233

234

235

236

237

238

239

240

241

243

248

0.00

21.7

117

148

206

295

429

622

736

822

871

900

922

938

949

958

966

972

977

982

986

989

992

998

1001

1005

1008

1017

1041 I I A. A. 1 1 .8. 1

Radial enthalpy distribution and fuel enthalpy are presented at elevation 29.4 nmn

Ma'drntn value of fuel enthalpy is 150.5 ca/g fuel (t-3.84 s)

1) All numerical values are presented at elevation Nvith peak povcr

G-8
#H1T (Idividual Chacteristics of Refabricated Fuel Rods I (PreErradia• l, Preirradiated Cladding) under IGR Tests -

Table G-1.5. Energy Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel

Rod #H1T

Energy Linear Energy of Clad-to-coolant heat

Time deposition') power') Fuel enthalpy') metal-water Leakage of energy]) transfer coefficienti)

(s) ( si (caL'g ti/fl) fuel) P°W/r) (kW/m) (ca/g I(kWfe)/emcFAPT fuel) reaction0 (caVg fuel) CAAR RK)6SCNI (kWVIK)

(caVgI fuel) FRA-T6 ISCANAIR FRAP-T6 FRAP-T6 SCAb/AIR ,FRAP-T6 SAAR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

5.71

30.8

38.9

54.1

77.3

113

163

193

216

229

236

242

246

249

252

254

255

257

258

259

260

260

262

263

264

265

267

273

0.00

22.2

82.6

108

162

253

366

358

,241

139

85.6

58.9

40.9

30.3

23.9

19.2

15.8

13.3

11.4

9.67

8.21

7.04

6.09

4.32

3.52

2.76

2.42

1.67

0.23

0.00

5.13

25.2

31.2

42.4

57.9

82.1

115

132

144

149

150

150

148

146

144

141

138

135

131

126

121

117

107

100

91.8

86.6

66.5

12.6

0.00

4.24

23.4

30.3

41.9

59.9

83.1

114

133

141

146

147

147

145

142

140

137

134

130

124

116

109

103

90.7

81.2

72.5

65.0

43.5

6.36

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.01

0.01

0.01

0.01

0.02

0.02

0.02

0.02

0.02

0.02

0.02

0.02

0.02

0.02

0.02

0.02

0.02-

0.00

0.00

3.42

5.41

9.05

16.0

26.4

41.2

46.0

49.9

55.2

60.4

66.6

72.6

78.1

83.9

89.6

95.7

107

120

131

137

142

155

162

172

177

200

260

0.00

0.01

3.29

5.60

9.63

16.2

24.6

38.2

49.2

51.4

55.6

60.4

65.1

70.4

75.0

80.4

85.0

90.6

99.3

119

132

139

146

160

171

180

189

212

256

0.00

0.03

6.50

8.23

11.3

20.8

26.3

14.8

1.46

1.89

2.03

2.07

2.10

2.10

2.09

2.07

2.03

3.22

6.80

11.8

18.1

13.8

12.4

10.1

9.08

7.90

7.28

5.13

0.54

0.00

0.10

6.60

9.08

13.5

20.9

27.6

31.8

1.03

1.44

1.61

1.66

1.69

1.71

1.71

1.71

1.70

2.12

5.48

20.6

24.0

20.0

17.2

13.6

11.6

10.2

8.99

5.84

0.19

1) All numerical values are presented at elevation with peak po%%r

G-9
M IT ta jd Cladding) idde iGR i ,Tests

Table G-1.6. Temperature Variation, Fission Gas Release and ZrO2 Thickness Vs. Time for Fuel

Rod #HMT Calculated by FRAP-T6 and SCANAIR Codes

Fuel centerline Fuel surface Clad outer Average

Time 1) temperaturel) Fission gas release ZrO2 2)

(s) (K) (K) (K) thickness

tMp-T6 SCANAI FRAP-T6 SCANAIR RAP-T6 [SCANAIR FRAP-T6 SCANAIR IR_-T6

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

'10.0

30.0

293

379

701

798

975

1242

1635

2145

2398

2559

2636

2668

2681

2677

2665

2646

2620

2590

2557

2521

2482

2440

2395

2250

2132

1952

1840

1414

497

293

362

666

775

954

1230

1572

2026

2331

2471

2556

2593

2601

2593

2575

2547

2519

2481

2443

2399

2354

2312

2259

2098

1921

1733

1560

1080

395

293

368

573

618

701

690

800

903

1092

1287

1398

1436

1443

1434

1420

1405

1405

1400

1338

1229

J1143

'1117

1109

1099

1091

1078

1066

985

479

293

355

572

629

710

805

929

1049

1122

1279

1419

1458

1467

1467

1461

1450

1437

1420

1387

1157

1011

956

935

909

887

864

840

737

391

293

328

404

408

414

427

434

516

824

1043

1110

1133

1147

1148

1142

1132

1114

1064

867

607

424

418

416

412

410

407

406,

401

382

293

321

390

394

399

407

413

426

701

996

1117

1153

1175

1188

1192

1190

1185

1167

1051

529

412

406

403

399

397,

395

394

389

376

0.00

0.06

0.22

0.30

0.47

0.81

1.61

3.30

5.07

7.79

10.7

14.1

15.7

16.1

16.2

16.2

16.2

16.2

16.2

16.3

16.3

16.3

16.3

16.3

16.3

16.3

16.3

.16.3

16.4

0.00

0.45

1.92

2.28

2.68

3.07

3.34

3.61

5.05

6.89

9.33

11.5

13.2

14.6

15.5

162

16.7

17.1

17.4

17.6

17.7

17.7

17.7

17.7

17.7

17.6

17.5

17.2

15.7

5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.01

5.02

5.03

5.05

5.06

5.08

5.09

5.10

5.10

5.10

5.10

5.10

5.10

5.10

5.10

5.10

5.10

5.10

5.10 U . I I A. I I A.

")All numerical values are presented at elevation with peak power

2

) Initial Z-O2thickness is 5 pm

G-10
#H1T IJT Cff-I M4ic of Rifabricýat~ Fi-k'&1 Rod f. , ' -

Mil d riiea dita ed Cddbi6g wider IGR Test

Table G-1.7. Mechanical Characteristics of Fuel Rod #H1T Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes

Clad outer Fuel hoop Fuel - clad gap Clad hoop Clad hoop Internal gas

Time temperaturel) straini) width') straint stressi) pressure

.(s) (K) (Ma (MPa)

FRAP-T6TSWANAIj FRAP-T6ISCANAI FRAP-T6 SCANAIR FRAP-T61SCANAIR FRAP-T6 SCANAIj FRAP.T61SCANAIM

0.0 293

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3A

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

328

404

408

414

427

434

516

824

1043

1110

1133

1147

1148

1142

1132

1114

1064

867

607

424

418

416

412

410

407

406

401

382

293

321

390

394

399

407

413

426

701

996

1117

1153

1175

1188

1192

1190

1185

1167

1051

529

412

406

403

399

397

395

394

389

376

0.00 1 0.00 1 0.03

0.10

0.53

0.66

0.92

1.33

1.99

3.08

3.76

4.48

4.89

5.24

5A2

5.36

5.27

5.14

5.02

4.88

4.72

4.49

4.24

4.02

3.83

3.37

3.08

2.69

2.46

1.59

0.23

0.05

0.26'

0.34

0.49

0.73

1.08

1.92

2.91

3.64

4.05

4.22

4.28

4.29

4.27

4.24

4.20

4.14

4.09

3.96

3.79

3.66

3.54

3.31

3.14

3.00

2.88

2.56

2.09

0.03

0.01

0.01

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.01

0.02

0.02

0.03

0.03

0.03

0.04

0.04

0.05

0.07

0.08

0.09

0.10

0.14

0.19

0.03

0.03

0.02

0.02

0.02

0.01

0.00

0.00

0.00

0.00

0.01 1 0.01

0.03

0.09

0.10

0.11

0.45

0.96

1.83

2AI

3.04

3.38

3.64

3.78

3.84

3.89

3.94

3.97

3.99

3.87

3.70

3.57

3.55

3.55

3.54

3.54

3.54

3.53

3.53

3.50

0.03

0.10

0.11

0.12

0.15

0.27

0.95

1.76

2.32

8.26

8.57

9.18

9.30

9.61

391

195

363

144

11.5

11.9

12.4

12.6

12.6

12.6

12.6

12.6

12.6

12.6

12.6

12.5

12.5

12.4

12.3

12.2

12.1

12.0

11.7

10.4

7.99

8.41

9.82

10.2

10.9

11.8

134

403

263

27.5

1.70

1.76

1.87

1.90

1.93

1.97

2.00

2.05

2.10

2.16

2.23

2.29

2.32

2.33

2.33

2.32

2.32

2.31

2.31

2.31

2.30

2.29

2.29

2.26

2.25

2.22

2.21

2.15

1.93

1.70

1.77

1.95

1.98

2.03

2.07

2.11

2.14

2.18

2.24

G-1I
#H1T Qc Cla$''Ubddingj) iindir IGiRTst I

Table G-1.8. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #H1T

Axial interval Energy deposition at infinite time Fuel enthalpy

from-to at time (t=3.84 s)

(mm)-(mm) caVg fuel J/g fuel per-unit ca!/g fuel Jig fuel per-unit

21.5-37.2 279 1168 1.00 151 631 1.00

37.2-52.9 270 1129 0.97 145 610 0.97

52.9-68.6 255 1067 0.91 138 576 0.91

68.6- 84.3 252 1054 0.90 136 569 0.90

84.3 - 100.0 249 1044 0.89 135 564 0.89

100.0- 115.7 250 1048 0.90 135 566 0.90

115.7- 131.4 246 1030 0.88 133 556 0.88

131.4- 147.1 243 1017 0.87 131 549 0.87

147.1 - 162.8 244 1024 0.88 132 553 0.88

162.8- 178.5 247 1035 0.89 133 559 0.89

300

• 250

•- 200

"U

150

0

-- 100

50

0

20 40 60 80 100 120

Axial coordinate (mm)

140 160 180

Fig. G-1.4. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6 Code

for Fuel Rod #HIT

G-12
#H1T I.___AMR______________

1.2 -. .

1.0

S 0.8 US - "-- - - -. :.-

o 0.6

Cn

0.4

0.2

2 3 4

Radial fuel coordinate (mm)

1.2-

Pus

1.0-

0.8 -

o 0.6 -

S 0.4

0.2

1 2 3 4

Radial fuel coordinate (mm)

Fig. G-1.5. U23s and Pu239 Radial Distributions of Energy Deposition for Fuel Rod M1IT

G-13
MI1T I Tz~d~j di isticsoRefabri~ated Fuel Rods ~ -.4

~ Chddin~f wider IGR Tests

1.2 I _____ ______ __ I _ ______ ______I _ _ _ _

0

0

1.0

0.8

0.6

4

0.4 -

1K II

0.2 -

1 2 3 4

Radial fuel coordinate (mm)

200

150

.,- 100

.5

50

0

1.0 1.5 2.0 2.5 3.0 3.5 4.0

Radial fuel coordinate (mm)

Fig. G-1.6. Radial Distributions of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #HIT

G-14
I#HIT I ~ ofRefabricmt& fuel Rodý

500

400

300

200 0I..

100

0

3000

2400

1800

E 1200

600

0

300

240

180 ,2-

120 "

60

0

0 1 2 3 4 5 6 7 8 9

Time (s)

10

35

28

0.

U

21~

144

.0OU

14

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. G-1.7. Energy and Temperature Characteristics Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes for Fuel Rod #H1T

G-15
#IfhT 'Si6#~jV ii Caddin- underIGcss<

2.5

2.0

i 1.5

1.0 4-JE

0.5

0.0

: FRAP-T6

' , .... SCANAIR

Internal gas pressure , Clad hoop stress

* * a -T

* ' ' * a

r---- ... "- . -

450

360

270

90

180

90

0

0 1 2 3 4 5

Time (s)

6 7 8 9 10

5

4

.E

0

0

0

0.15

0.12

E

E

0.09 .s

•0

0.06 e9

0.03

0.00

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. G-1.8. Cladding Mechanical Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #H1T

G-16
#H1T tin ~ d~ Cidhg Fueldir I

10

8

0

0

6

4

3000

2400

1800

1200 I-E

600

0

2

0

20'

15

0 1 2 3 4 5 6 7 8 9 10

Time (s)

10

€• 10

5

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. G-1.9. Fuel Strain and Fission Gas Release Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #H1T

G-17
#H1T I 1dvui hrd iisfearcedFeRdS i

Table G-1.9. Some Results of PIE for Fuel Rod #H1T

Characteristic Value

I Measured parameters of cladding oxidation and cladding

deformation

1.1 Cladding thickness at elevation 90 mm for different azimuthal

angles (mm):

00 705

900 700

1800 705

2700 700

1.2 ZrO2 thickness at elevation 90 mm for different azimuthal angles

(mm):

00 5

900 5

1800 5

2700 5

1.3 caZr(O) thickness at elevation 90 mm for different azimuthal angles

(mm):

00 0

900 0

1800 0

2700 0

1.4 Clad hoop strain axially averaged (%) 1.4

2 Measured parameters for FGR analysis

2.1' Internal gas composition (% by volume):

He 85.42

N2 0.14

02 0.02

Ar 0.004

CO2 0.01

Kr 1.39

Xe 13.02

2.2 Free gas volume (cm 3

) 5.52

2.3 Gas pressure inside fuel rod under normal condition (MPa) 1.913

2.4 Kr concentration in fuel (cm3

/g fuel) 0.13

3 Measured parameters of cladding hydriding

3.1 Coefficient of hydride orientation (per-unit)

3.2 Hydrogen concentration (% by weight) 8.2 10-'

G-18
#H1T ofRefabriceted Fuel Rodj & 

'

f~~~~e (rrrdk1T ifaited Cladding) uindir IGR-Tes6s

Table G-1.10. General Characteristic of Fuel Rod #H1T

Parameter Unit Value

Experiment FRAP-T6 SCANAIR

I Type of coolant --- water water water

2 Burnup MWd/kg U .,49.2 49.2 49.2

3 Energy deposition in fuel rod cal/g fuel 253 253 253

4 Peak fuel enthalpy cal/g fuel 151 147

5 Peak fuel temperature K - 2681 2601

6 Peak clad temperature K 1148 1192

7 Fuel rod failure Yes, No No No -

8 Type of failure:

- cladding rupture due to ballooning Yes, No No No -

- cladding rupture due to PCMI Yes, No No No -

- fragmentation of fuel rod Yes, No No -

9 Failure time s - -

10 Fuel enthalpy at failure cal/g fuel - - -

11 Outer cladding temperature at failure K

12 Internal gas pressure at failure MPa - --

13 ZrO2 thickness after test Pm 5 5.10 -

14 Residual clad hoop strain:

- peak value for ballooning area %- - -

- other location]) % 1.4 2.82 1.83

15 Kr concentration in internal gas % by volume 1.39 2.25 2.49 15 composition after test

16 Xe concentration in internal gas % by volume 13.02 13.50 14.95

16 composition after test

17 Kr concentration in fuel after test crm3/g fuel 0.13 0.15 1 0.17

')Calculated values by FRAP-T6 and SCANAIR codes arc average along height of fuel rod excluding ballooning region

F

G-19

ThdVI~duaP6

I APPE ND)

T2 T wi;der iýies

G-21
#H2T I ~Pr!~ri' l aaedCladig)under, IRtst S,--

Fig. G-2.1. Appearance of Fuel Rod #H2T (photographs and X-ray photograph)

G-22
#H2T Individual &iieeristics of Refabricated Fuel Rods-

(Preirradiatedfpe, Preirradiated Cladding) under IGR Tests

Position I

Pncitinn9

Fig. G-2.2. Cross-Section and Cladding Microstructure for Fuel Rod #t12T at 85 mm Elevation

G-23
#H2T- IIndlividual Characted-fiiUofRefabricated Fuel Rods

'(Preirradiated Fue4r1%radiatcd Cladding) under IGR Tests

Fig. G-2.3. Cross-Section and Cladding Microstructure for Fuel Rod #H2T at 115 mm Elevation

G-24
#H2T I (?reirradfl)5.Urradiated Cladding) wider IGR Tests -j -

Position I

Position 1

Fig. G-2.4. Cross-Section and Cladding Microstructure for Fuel Rod #112T at 160 mm Elevation

G-25
I I

I lndiyia~Cii fi~i~i'ifRefabricat&I Fuel Rods I #H2T i~d Ii~cd Cladding under IGR TestsA-~ I

Position I

Fig. G-2.5. Fuel Microstructure for Fuel Rod #H2T at 115 mm Elevation

G-26
#H2T I~id 4 ~iii ~ of kiec efaricated Rods'- 'ie . :

I ~<rc~ndxatd ~feiir diid'Claddi~ng) 22cdr IGRktest..-

Table G-2.1. Time Dependent Energy Characteristics of Fuel Rod #H2T

Reac- Cumulative number of fissions Power Energy

tor in fuel rod (fiss) of fuel deposition

Time energy rod in fuel rod

(s) deposi- U 235 u Pu2 39 Pu24' Oter Tota (kW) t i(n) x10" "13 X1014 x10"14 iso- x10"14 fuel

n(J) topes

x10-

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

9.0

10.0

20.0

30.0

00

0.000 1 0.000 1 0.000 - 0.000 1 0.000 1 0.000 0.000 1 0.000 1 0.000

0.773

4.870

7.020

10.30

15.30

23.30

36.10

53.80

69.50

79.60

85.60

89.10

91.20

92.60

93.50

94.10

94.60

95.00

95.30

95.50

95.80

96.00

96.40

96.70

96.90

97.10

97.50

97.80

99.10

99.50

100.0

0.073

0.459

0.662

0.968

1.440

2.200

3.410

5.070

6.550

7.500

8.060

8.390

8.590

8.720

8.810

8.870

8.910

8.950

8.980

9.000

9.020

9.040

9.080

9.110

9.130

9.150

9.190

9.220

9.340

9.380

9.460

0.016

0.100

0.145

0.212

0.315

0.481

0.745

1.110

1.430

1.640

1.760

1.830

1.880

1.910

1.930

1.940

1.950

1.960

1.960

1.970

1.970

1.980

1.980

1.990

2.000

2.000

2.010

2.010

2.040

2.050

2.070

0.105

0.662

0.955

1.400

2.080

3.180

4.920

7.320

9.460

10.80

11.60

12.10

12.40

12.60

12.70

12.80

12.90

12.90

13.00

13.00

13.00

13.10

13.10

13.20

13.20

13.20

13.30

13.30

13.50

13.50

13.70

0.043

0.269

0.388

0.568

0.846

1.290

2.000

2.980

3.850

4.400

4.730

4.930

5.040

5.120

5.170

5.210

5.230

5.250

5.270

5.280

5.300

5.310

5.330

5.350

5.360

5.370

5.390

5.410

5.480

5.510

5.550

0.079

0.495

0.715

1.050

1.560

2.380

3.680

5.480

7.080

8.110

8.710

9.070

9.290

9.420

9.520

9.580

9.630

9.670

9.700

9.730

9.750

9.770

9.810

9.840

9.870

9.890

9.930

9.960

10.10

10.10

10.20

0.222

1.400

2.020

2.960

4.400

6.720

10.40

15.50

20.00

22.90

24.60

25.60

26.20

26.60

26.90

27.10

27.20

27.30

27.40

27.50

27.60

27.60

27.70

27.80

27.90

28.00

28.10

28.10

28.50

28.60

28.90

1.280

7.270

10.80

16.40

25.90

41.70

64.70

75.00

53.10

31.80

18.70

11.30

7.170

4.780

3.330

2.420

1.850

1.570

1.350

1.170

1.020

0.904

0.693

0.560

0.472

0.409

0.356

0.291

0.078

0.041

0.000

2.490

15.70

22.60

33.10

49.20

75.10

116.0

173.0

224.0

256.0

276.0

287.0

294.0

299.0

302.0

304.0

306.0

307.0

308.0

309.0

310.0

311.0

312.0

314.0

315.0

315.0

317.0

318.0

324.0

326.0

333.0

0.000

10.40

65.70

94.60

139.0

206.0

314.0

486.0

724.0

938.0-

1072.

1155.

1201.

1231.

1252.

1264.

1273.

1281.

1285.

1289.

1293.

1298.

1302.

1306.

1314.

1319.

1319.

1327.

1331.

1356.

1365.

1394.

Maximum value of power is 76.5 kW (t - 3.15 s).

1) Current energy deposition per maximum energy deposition (at infinite time)

G-27
#H2T I 4

Table G-2.2. Axial Energy Characteristics of Fuel Rod #H2T

Axial Cumulative number of fissions Maxi- Energy deposition

coordi- at axial interval (fiss) mum at infinite time*

nate power of

from U 2 5 U 23

S Pu2 " Pu2 ' Other Total fuel rod callg J/g perlower Xn0-d3 Xl0-1 Xl0.13 XI0.13 iso- xl0"3 (kw) fuel fuel unit 3)

end of rs3.15s topes 

fuel rod 1 I10 

(mm) x 10 o

10.0

15.0

20.0')

25.0

30.0

35.0

40.0

45.0

50.0

55.0

60.0

65.0

70.0

75.0

80.0

85.0

,90.0

95.0

100.0

105.0

110.0

115.0"

120.0

125.0

130.0

135.0

140.0

145.0

150.0

155.0

160.0

165.0

170.02)

175.0

180.0

185.0

0.000

0.000

1.750

2.920

3.060

3.070

3.050

3.000

2.880

2.800

2.860

2.940

3.020

3.060

3.200

3.310

3.380

3.380

3.340

3.320

3.350

3.370

3.390

3.420

3.300

3.240

3.280

3.310

3.300

3.270

3.030

2.890

1.140

0.000

0.000

0.000

0.000

0.000

3.460

5.770

6.980

7.030

6.980

6.860

6.840

6.820

6.740

6.800

6.950

7.010

7.050

7.110

7.120

7.020

6.910

6.840

6.840

6.860

6.890

6.930

6.970

7.040

7.110

7.160

7.170

7.110

6.910

6.830

2.680

0.000

0.000

0.000

0.000

0.000

2.600

4.330

4.560

4.590

4.560

4.480

4.450

4.430

4.390

4.430

4.540

4.580

4.630

4.670

4.700

4.650

4.570

4.520

4.530

4.550

4.560

4.590

4.600

4.630

4.670

4.700

4.720

4.670

4.520

4.440

1.750

0.000

0.000

0.000

0.000

0.000

1.060

1.770

1.870

1.890

1.870

1.840

1.850

1.850

1.820

1.830

1.870

1.890

1.890

1.890

1.890

1.860

1.820

1.800

1.800

1.800

1.820

1.820

1.850

1.880

1.890

1.900

1.910

1.890

1.860

1.840

0.722

0.000

0.000

0.000

0.000

0.000

1.840

3.070

3.450

3.440

3.440

3.430

3.430

3.430

3.430

3.430

3.430

3.430

3.440

3.440

3.450

3.460

3.460

3.460

3.470

3.470

3.460

3A60

3.450

3.440

3.430

3.410

3.380

3.360

3.330

3.300

1.310

0.000

0.000

0.000

0.000

0.000

5.450

9.080

9.570

9.620

9.550

9.390

9.250

9.150

9.140

9.260

9.500

9.600

9.780

9.950

10.10

9.960

9.800:,

9.720

9.750

9.790

9.840

9.900

9.820

9.810

9.920

9.990-

10.00

9.900

9A80

9.240

3.630

0.000

0.000

0.000

0.000

0.000

1.440

2.410

2.540

2.550

2.530

2.490

2.450

2.420

2.420

2.450

2.520

2.540

2.590

2.640

2.660

2.640

2.590

2.570

2.580

2.590

2.610

2.620

2.600

2.600

2.630

2.650

2.650

2.620

2.510

2.450

0.963

0.000

0.000

0.000

0.000

0.000

319.0

313.0

329.0

329.0

329.0

329.0

325.0

322.0

326.0

328.0

328.0

329.0

333.0

336.0

339.0

341.0

341.0

342.0

343.0

343.0

343.0

344.0

339.0

335.0

336.0

335.0

335.0

335.0

329.0

325.0

325.0

0.000

0.000

0.000

0.000

0.000

1335.

1310.

1377.

1377.

1377.

1377.

1360.

1348.

1365.

1373.

1373.

1377.

1394.

1406.

1419.

1427.

1427.

1432.

1436.

1436.

1436.

1440.

1419.

1402.

1406.

1402.

1402.

1402.

1377.

1360.

1360.

0.000

0.000

0.000

0.00

0.00

0.93

0.91

0.96

0.96

0.96

0.96

0.94

0.94

0.95

0.95

0.95

0.96

0.97

0.98

0.99

0.99

0.99

0.99

1.00

1.00

1.00

1.00

0.99

0.97

0.98

0.97

0.97

0.97

0.96

0.94

0.94

0.00

0.00

0.00 I

* All numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate E 2.5 mm

I) Initial coordinate of fuel is 19.5 nun

2) End coordinate of fuel is 169.5 mmn

3) Current value per maximum value

G-28
#H2T ,[I ýd Mo-t~ of Refai~bicate Fuel R6dS',

~~1 ~ I~-ei iioditeCldding) yundei IG-RT -st

Table G-2.3. Radial Energy Characteristics of Fuel Rod #H2T

Coordinates of fuel zones (mm)

Characteristics* 1 zone 2 zone 3 zone 4 zone

1.2 - 2.811 2.811-3.432 3.432-3.704 3.704-3.790

Number of fissions x 10"14 (fiss) 4.810 2.820 1.380 0.450

Power of fuel rod') (kW) 12.50 7.340 3.600 1.170

U2" Energy deposition2 ) (cal/g fuel) 109.0 106.0 104.0 102.0

Energy deposition2

) (Jig fuel) 456.0. 444.0 435.0 427.0

Energy deposition3) (per-unit) 1.000 0.972 0.954 0.936

Number of fissions X10"12 (fiss) 10.90 6.120 2.820 0.852

Power of fuel rod') (kW) 0.280 0.158 0.073 0.022

U238 Energy deposition 2

) (cal/g fuel) 2.430 2.280 2.100 1.900

Energy deposition2

) (J/g fuel) 10.20 9.540 8.790 7.950

Energy deposition3) (per-unit) 1.000 0.938 0.864 0.782

Number of fissions x 10"14 (fiss) 5.660 3.850 2.640 1.500

Power of fuel rod1) (kW) 15.20 10.30 7.090 4.020

Pu3 9 Energy deposition2

) (calg fuel) 133.0 150.0 206.0' 351.0

Energy deposition2) (J/g fuel) 557.0 628.0 862.0 1469.

Energy deposition3) (per-unit) 0.379 0.427 0.587 1.000

Number of fissions x10"13 (fiss) 22.00 15.60 11.20 6.700

Power of fuel rod1) (kW) 5.810 4.130 2.960 1.770

Pu24' Energy deposition2) (callg fuel) 50.60 59.90 86.10 154.0

Energy deposition2) (J/g fuel) 212.0 251.0 360.0 645.0

Energy deposition3) (per-unit) 0.329 0.389 0.559 1.000

Number of fissions x10"' (fiss) 4.770 2.940 1.710 0.815

Other Power of fuel rod' (kW) 0.013 0.008 0.005 0.002

isoto- Energy deposition2) (cal/g fuel) 0.110 0.113 0.132 0.189

pes Energy deposition 2

) (J/g fuel) 0.460 0.470 0.550 0.790

Energy deposition3) (per-unit) 0.582 0.598 0.698 1.000

Number of fissions X10"14 (fiss) 12.80 8.300 5.190 2.640

Power of fuel rod') (kW) 33.80 22.00 13.70 6.990

Total Energy deposition2) (caVg fuel) 294.0 319.0 399.0 609.0

Energy deposition 2

) (J/g fuel) 1231. 1335. 1670. 2549.

Energy deposition3) (per-unit) 0.483 0.524 0.655 1.000

I) at time of 3.15 s, 2) at infinite time, 3) Current value per maximum value.

* All numerical values of characteristics were calculated for undamaged part of fuel stack only (See Table C.2.1.)

G-29
10ir ýMOM M Fuelf&6;)ýI Rýod #H2T I rt44 Cld'adding) underJORTst

Table G-2.4. Fuel Entbalpy Vs. Time Calculated by FRAP-T6 Code for Fuel Rod 1#H2T

Enthalpy at fuel radius Energy deposition Time E calpa fuel) Fuel enthalpy I) in fuel rod

(S) 1:1:20 =mm 2.82mm [ 3.47 mn 3.79 mm cal/g fuel Ji fuel fg fuel J/g fuel

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

42

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

4.89

16.8

22.8

32.1

46.5

69.7

i07

158

204

233

248

256

260

260

258

256

253

249

245

240

236

231

219

207

195

183

140

25.9

0.00

4.85

16.3

21.9

30.4

43.6

64.7

97.8

144

183

204

213

217

217

214

210

205

200

195

190

186

181

177

168

157

145

136

110

24.3

0.00

4.75

15.0

19.6

26.2

36.6

47.9

71.3

100.0

129

148

162

166

163

159

155

151

147

143

140

138

136

134

126

115

108

103

89.5

23.0

0.00

4.60

13.4

16.7

21.0

27.8

28.9

38.0

50.9

87.8

110

129

132

127

125

122

120

118

116

115

114

113

112

104

93.0

89.6

87.3

79.4

22.2

0.00

4.83

16.0

21.4

29.4

42.0

60.3

91.1

133

171

195

208

213

213

211

208

204

200

196

192

188

184

180

171

159

149

140

113

24.4

0.00

20.2

66.9

89.5

123

176

253

382

557

719

816

870

891

892

883

869

854

* 837

819

803

787

771

756

715

667

625

588

472

102

0.00

2.50

15.7

22.5

32.9

49.0

74.8

116

172

223

256

275

286

294

299

302

304

306

307

308

309

310

311

312

313

314

315

318

326

0.00

10.5

66.0

94.3

138

205

313

485

723

936

1073

1152

1200

1233

1252

1264

1274

1280

1286

1291

1295

1298

1302

1308

1313

1317

1321

1332

1365

Radial enthalpy distribution and fuel enthalpy are presented at elevation 117.0 mm

Maximum value of fuel enthalpy is 213.3 cal/g fuel (t=4.12 s)

') All numerical values are presented at elevation %Nith peak power

G-30
#H2T i' I

Table G-2.5. Energy Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel

Rod #H2T

Energy Linear Energy of Clad-to-coolant heat

( s) (cag fiuel) (kW/m) (cal/g fuel) reaction') (cal/g fuel) (kW/m2K) (s) (k/m)(caeag cal/ fue) fuel)

RA-6 I s FRAP-T6 FRAP-T6 I AN FRAP-T6 SCANAIR

0.0

1.0

2.0

2.2

2A

2.6

2.8

3.0

32

3.4

3.6

3.8

4.0

4.2

4A

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

2.58

162

23.2

33.9

50.6

77.2

119

178

231

264

284

296

304

308

311

314

315

317

318

319

320

321

322

323

324

325

328

336

0.00

9.02

51.3

75.5

115

181

291

452

525

372

221

132

79.6

48.1

32.2

22.5

16.5

12.7

10.8

9.31

8.08

7.06

625

4.81

3.89

3.28

2.86

2.03

0.29

0.00

4.83

16.0

21.4

29.4

42.0

60.3

91.1

133

171

195

208

213

213

211

208

204

200

196

192

188

184

180

171

159

149

140

113

24A

0.00

2.17

13.7

18.8

27.5

40.8

583

89.0

133

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.01

0.05

0.12

0.19

0.26

0.31

0.36

0.40

0.43

0.45

0.46

0.48

0.49

0.50

0.50

0.50

0.50

0.50

0.50

0.00

0.02

1.40

2.75

5.05

8.66

16.1

26.9

39.8

43.3

48.9

55.4

62.2

70.0

77.2

84.3

91.2

97.7

104

110

.116

121

126

149

169

180

190

219

316

0.00

0.01

0.54

1.65

3.88

7.73

13.4

25.3

32.5

0.00

0.03

3.27

5.12

8.03

11.5

22.1

29.6

6.44

1.79

2.12

2.13

2.16

2.20.

2.20

2.17

2.13

2.09

2.04

1.99

1.94

1.90

1.87

8.48

12.1

10.5

9.35

6.69

1.25

0.00

0.10

3.00

5.03

8.31

13.6

21.3

31.8

1.34

.5. .5. .5. A a - -

1) All nunerical values are presented at elevation with peak power

G-31
#H2T I 1zdivr&uaY~~~i efabiic~t~d Fuel Rods.~ - -,

~Preirrad~ ~T~T~ed Cladding) udder IGR~Tests -!

Table G-2.6. Temperature Variation, Fission Gas Release and ZrO1 Thickness Vs. Time for Fuel

Rod #H2T Calculated by FRAP-T6 and SCANAIR Codes

Average

Time Fuel centerline Fuel surface Clad outer Fission gas release ZrO2g2) (s) temperature'1 temperature temperature thickness

(K) (K) (K)

FRAP-T6 SCANAIR FRAP-T6 SCANAIR FRAPT6 SCANAI FRAP-T6 SCANAIR IFRA-T6

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

376

556

642

772

968

1272

1737

2299

2690

2890

2987

3034

3054

3056

3048

3033

3014

2991

2966

2939

2910

2880

2799

2715

2625

2527

2114

685

293

329

510

589

722

925

1190

1659

2255

293

371

506

555

617

712

727

852

1026

1503

1781

1994

2027

1977

1951

1923

1895

1868

1847

1835

1825

1812

1799

1700

1568

1526

1497

1397

633

293

325

480

534

613

712

800

874

1200

293

352

395

401

408

414

429

437

636

1056

1236

1241

1258

1278

1277

1263

1242

1219

1195

1168

1142

1121

1102

694

415

412

410

405

387

293

308

384

388

393

399

407

426

922

0.00

0.12

0.51

0.80

1.22

1.92

3.23

5.28

7.65

11.8

16.8

26.0

40.4

48.5

49.4

49.5

49.6

49.6

49.6

49.6

49.6

49.6

49.6

49.6

49.7

49.7

49.7

49.7

49.7

0.00

0.24

1.11

1.62

2.16

2.62

3.01

3.41

4.48

5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.02

5.07

5.12

5.19

5.26

533

538

5.42

5.44

5.46

5.48

5.49

5.50

5.50

5.50

5.50

5.50

5.50

5.50 _____ .1 1 _____ I I Z _____ 1. &

1)All numerical values am prsent at elevation with peak power

2)Initial Zrz thickness is 5 tan

G-32
#H2T 'k e'47c rraiad Cladding) under IGR'Tss

Table G-2.7. Mechanical Characteristics of Fuel Rod #H2T Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes

Clad outer Fuel hoop Fuel - clad gap Clad hoop Clad hoop Internal gas Time temperature) strain' width) strain" stressi _ pressure

(S A KE) -T(0___) (MM) (00) .(M6a) (MPa)

57&7RA-T6 ;CANAIR nWAPT61SCANAIM MRA-T6 SCANAI HRA-T61SCANAII FRAPT61SCANAIM FRA-T61SCANAIM

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

.7.5

8.0

10.0

30.0

293

352

395

401

408

414

429

437

636

1056

1236

1241

1258

1278

1277

1263

1242

1219

1195'

1168

1142

1121

1102

694

415

412

410

405

387

293

308

384

388

393

399

407

426

922

0.00

0.12

0.42

0.57

0.78

1.11

1.63

2.49

3.62

0.00

0.02

0.16

0.21

0.31

0.48

0.71

1.19

2.81

0.04 1 0.03

4.79

5.20

5.48

5.60

6.07

6.01

5.93

5.84

5.75

5.64

5.53

5.41

5.30

5.18

4.84

4.43

4.06

3.73

"2.67

0.17

0.04

0.02

0.02

0.01

0.00

0.00

0.00

0.00

0.00

0.31

0.29

0.29

0.27

0.27

0.28

0.28

0.28

0.29

0.29

0.30

0.30

0.30

0.32

0.33

0.35

0.36

0.40

0.50

0.03

0.03

0.03

0.02

0.02

0.01

0.00

0.00

0.01

0.05

0.08

0.09

0.10

0.12

0.57

1.27

2.22

3.17

11.6

11.6

11.6

11.6

11.6

11.6

11.6

11.6

11.6

11.7

11.8

11.8

11.8

11.6

11.4

11.4

11.4

11.4

11.3

0.01

0.02

0.08

0.09

0.10

0.12

0.15

0.36

1.65

8.90

9.06

9.54

9.71

9.93

21.8

10.6

296

366

12.6

13.8

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

8.22

8A1

9.17

9.51

10.0

10.7

11.6

206

40.2

1.70

1.77

1.85

1.88

1.92

1.97

2.02

2.09

2.17

2.27

2.39

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

1.70

1.75

1.85

1.88

1.92

1.96

1.99

2.03

2.06

" All numerical valucs are presented at elevation with peak povr

G-33
#H2T

IndivFuellRodi 'I

ý.Id~tg Jund R -Tikils-i

Table G-2.8. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #H2T

Axial interval Energy deposition at infinite time Fuel enthalpy

from-to at time (t=4.12 s)

(mm)-(mm) calg fuel J/g fuel per-unit cal/g fuel J/g fuel per-unit

19.5- 34.5 322 1347 0.94 200 838 0.94

34.5 -49.5 328 1376 0.96 204 856 0.96

49.5 -64.5 325 1361 0.95 202 846 0.95

64.5 - 79.5 329 1379 0.96 205 857 0.96

79.5-94.5 337 1412 0.98 210 878 0.98

94.5-109.5 342 1431 1.00 212 890 1.00

109.5 - 124.5 343 1438 1.00 213 894 1.00

124.5 - 139.5 338 1417 0.99 210 881 0.99

139.5 - 154.5 335 1404 0.98 208 873 0.98

154.5- 169.5 328 1376 0.96 204 855 0.96

350

• 300

250

200

IE

150

100

u 50

0

0 20 40 60 80 100

Axial coordinate (mm)

120 140 160 180

Fig. G-2.6. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6 Code

for Fuel Rod #-H2T

G-34
#H2T kCladdin06iiicei~IGR ~~ Tes",Z

1.2

i

U

0

0

1.0

0.8

0.6

0.4

0.2

2 3

Radial fuel coordinate (nam)

4

1.2

E

E

C

1.0

0.8

0.6

0.4

0.2

1 2 3 4

Radial fuel coordinate (mm)

Fig. G-2.7. U23s and Pu2 9Radial Distributions of Energy Deposition for Fuel Rod #H2T

G-35
#H2T IýPrhialkjYel Mt Cladding)udr O c

1.2 -p

I)

I..

0

*0

t

1.0

0.8

0.6

.4 4 4

.4 4 +

0.4 -1 II

0.2 i

1 2 3 4

Radial fuel coordinate (mm)

300

250

a- 200

,•- 150

0..

100

50

0

• : ~---I- 1.0s

---- 2.Os

- =--- 3.0 s

-.- 4.1s

1.0 1.5 2.0 2.5 3.0 3.5 4.0

Radial fuel coordinate (mm)

Fig. G-2.8. Radial Distributions of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #H2T

G-36
#H2T I ~n~datdY~~eiraiated Claddin-g) aiie IOR Tests,_'

600

500

- 400

0

• 300

I,.-

200

100

0

4)

U

a.

a

4)

4)

a

w

0 1 2 3 4 5 6 7 8 9 10

Time (s)

3500 35

a.

4)

30

25

20

15 -

0

0

10 6

5

t4

0

0 1 2 3 4 5 6, 7 8 9 10

Time (s)

Fig. G-2.9. Energy and Temperature Characteristics Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes for Fuel Rod #H2T

G-37
#H2T MwI M1~lizl'lir~f..Kfabrcatc Fuel RodsW

I~(PrY~L~d Clad ding unideiiIGR-Tst

2.5

2.0

E 1.5

9

1.0

E

0.5

0.0

FRAP-T6 ....- SCANAIR

S--Internal gas pressure

Clad hoop stress

__ ------K

700

560

420

0

280 .

Cu

U

140

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

15

12

0.50

0.

0

9

6

C- Cu Co

Cu

U

U

3

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. G-2.10. Cladding Mechanical Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #H2TG-38
#H2T n o Rfhbric&iFe R~4

te I~l irated Cliddig mdr IRTsUs

0

0

0•

0

4)

10.0

8.0

6.0

4.0

2.0

0.0

3500

2800

2100

E

0.

14o0

700

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

60

0ý

is

to

4)

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. G-2.11. Fuel Strain and Fission Gas Release Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #H2T

G-39
#H2T (P'i Cladding) under IGR Tss

Table G-2.9. Some Results of PIE for Fuel Rod #H2T

Characteristic Value

I. Measured parameters of cladding oxidation and cladding

deformation

1.1. Cladding thickness at elevation 115, 85, 160 mm correspondent to

different azimuthal angles (11m):

00 690 663 480

900 667 663 677

1800 691 R 691

2700 690 649 691

1.2. ZrO2 thickness at elevation 115, 85, 160 mm correspondent to

different azimuthal angles (pm):

00 10 15. 10

900 10 15 10

1800 10 18 10

2700 10 15 8

1.3. aZr(O) thickness at elevation 115, 85, 160 mm correspondent to

different azimuthal angles (pm):

00 0 15 8

900 0 10 10

1800 0 10 8

2700 0 10 8

1.4. Clad hoop strain at elevation 115, 85, 160 mm, respectively (%) 7.9 12.6 11.4

2. Measured parameters for FGR analysis

2.1. Internal gas composition (% by volume):

He

N2

02

Ar

CO2

Kr

Xe

2.2. Free gas volume (cm3)

2.3. Gas pressure inside fuel rod under'normal condition (MPa)

2.4. Kr concentration in fuel (cm 3

/g fuel)

3. Measured parameters of cladding hydriding

3.1. Coefficient of hydride orieniation (per-unit)

3.2. Hydrogen concentration (% by weight)

G40
#H2T I ~ of Refaricad Fue 6ods ~~~ (Piirr ta~1a ~'rraiatmi Claddin) unde'r IGR Tetjs

Table G-2.10. General Characteristic of Fuel Rod #H2T

Parameter Unit Value

Experiment FRAP-T6 SCANAIR

1 Type of coolant -- water water water

2 Burnup MWd/kg U 47.9 47.9 47.9

3 Energy deposition in fuel rod cal/g fuel 333 333 333

4 Peak fuel enthalpy cal/g fuel - 213 -

5 Peak fuel temperature K - 3057 -

6 Peak clad temperature K - 1280 -

7 Fuel rod failure Yes, No Yes Yes -

8 Type of failure:

- cladding rupture due to ballooning Yes, No Yes Yes -

- cladding rupture due to PCMI Yes, No No No -

- fragmentation of fuel rod Yes, No No - -

9 Failure time s - 3.60 -

10 Fuel enthalpy at failure cal/g fuel - 195 -

11 Outer cladding temperature at failure K - 1236 -

12 Internal gas pressure at failure MPa - 2.39 -

13 ZrO2 thickness after test pm 8-18 5.50 -

14 Residual clad hoop strain:

- peak value for ballooning area % 12.6 11.28 -

- other location') % 7.9,11.4 3.26 -

15 Kr concentration in internal gas % by volume 6.35 - composition after test

16 Xe concentration in internal gas % by volume 38.03

composition after test

17 Kr concentration in fuel after test cm3/g fuel 0.09 -

"Calculated values by FRAP-T6 and SCANAIR codes are average along height of fuel rod excluding ballooning region

G-41

G-43
#H3T I FulRd

PositionWf

.tic

Fig. G-3.1. Appearance of Fuel Rod #H3T (photographs and X-ray photograph)

G-44
#H3T ,'"DowI

IQ r=

Position 2

Fig. G-3.2. Cross-Section and Cladding Microstructure for Fuel Rod #H3T at 55 mm Elevation

G-45
#H3T [(Prelfiia_ a e irmi1cdW Cladding) under 1GR Tcstsi

Fig. G-3.3. Cross-Section and Cladding Microstructure for Fuel Rod #H3T at 80 mm Elevation

G-46
#H3T ~fRefabricated FuelR~S~

Fig. G-3.4. Cross-Section and Cladding Microstructure for Fuel Rod #H3T at 130 mm Elevation

G-47
#H3T (Prirr54( A • i•d aCladding) unde ICR Tests

Position 1

,-46

Fig. G-3.5. Fuel Microstructure for Fuel Rod #H3T at 80 mm Elevation

G-4
#H3T __________________ os'f Refabricae FulRd ;. :

Tm.-aja'd@M k~d~" Claddjoing) der 10kRTc1itTable G-3.1. Time Dependent Energy Characteristics of Fuel Rod #H3T

Reac- Cumulative number of fissions Power Energy

tor in fuel rod (fiss) of fuel deposition

Time energy rod in fuel rod

(s) deposi- U2 35 U 23 8 pu2 39 pu 24

1 Other Total (kW)

n'Other 1) Total cal/g J/g fuel tin) l 0-14 XIO-13 x10-14 xIO"14 iso- xlO"14 fuel

(%) 1topesx10O11

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

9.0

10.0

20.0

30.0

00

0.000

0.865

4.220

5.520

7.320

10.10

14.80

23.20

36.90

54.70

70.10

80.00

85.70

89.20

91.20

92.60

93.50

94.10

94.60

95.00

95.30

95.60

95.80

96.30

96.60

96.90

97.10

97.50

97.80

99.10

99.50

100.0

0.ooo

0.089

0.433

0.566

0.751

1.040

1.520

2.380

3.790

5.610

7.190

-8.200

8.800

9.150

9.360

9.500

9.590

9.660

0.000

0.022

0.107

0.140

0.186

0.257

0.376

0.589

0.939

1.390

1.780

2.030

2.180

2.270

2.320

2.350

2.380

2.390

2.400

2.410

2.420

2.430

2.440

2.450

2.460

2.460

2.470

2.480

2.490

0.000

0.137

0.668

0.872

1.160

1.600

2.340

3.660

5.840

8.640

11.10

12.60

13.60

14.10

14.40

14.60

14.80

14.90

15.00

15.00

15.10

15.10

15.10

15.20

15.30

15.30

15.30

15.40

15.50

15.70

15.70

15.90

0.000

0.057

0.276

0.360

0.478

0.660

0.966

1.510

2.410

3.570

4.580

5.220

5.600

5.820

5.960

6.050

6.100

6.150

6.180

6.200

6.220

6.240

6.260

6.290

6.310

6.330.

6.340

6.360

6.390

6.470

6.500

6.560

0.000

0.108

0.526

0.687

0.912

1.260

1.840

2.880

4.600

6.810

8.730

9.960

10.70

11.10

11.40

11.50

11.60

11.70

11.80

11.80

11.90

11.90

11.90

12.00

12.00

12.10

12.10

12.10

12.20

12.30

12.40

12.50

0.000

0.284

1.390

1.810

2.410

3.320

4.860

7.610

12.10

18.00

23.00

26.30

28.20

29.30

30.00

30.40

30.70

30.90

31.10

31.20

31.30

31.40

31.50

31.60

31.70

31.80

31.90

32.00

32.10

32.60

32.70

33.00

0.000

1.630

5.280

7.060

10.30

16.60

29.10

51.30

77.50

84.30

59.40

35.40

20.80

12.60

8.010

5.350

3.750

2.730

2.170

1.840

1.570

1.360

1.190

0.885

0.697

0.576

0.493

0.426

0.344

0.090

0.047

0.000

0.000

3.210

15.70

20.50

27.20

37.50

55.00

86.00

137.0

203.0

260.0

297.0

319.0

332.0

339.0

345.0

348.0

351.0

353.0

354.0

356.0

357.0

358.0

360.0

361.0

363.0

364.0

365.0

367.0

373.0

376.0

384.0

0.000

13.40

65.70

85.80

114.0

157.0

230.0

360.0

573.0

850.0

1088.

1243.

9.700

9.740

9.780

9.800

9.830

9.880

9.910

9.940

9.960

10.00

10.00

1335.

1390.

1419.

1444.

1457.

1469.

1478.

1482.

1490.

1494.

1499.

1507.

1511.

1520.

1524.

1528.

1536.

1561.

1574.

1607.

10.20

10.20

10.30

2.520

2.530

2.550 I - - .1. I 1 I J. a I -

Maximum value of power is 86.1 kW (t - 3.35 s).

I) Current energy deposition per maximum energy deposition (at infinite time)

G-49
#H3T Iuidli efhbncae dFuddn R.l ,el 

I~ ~~1r a~~~~ddCadding) wider IGRTcits,

Table G-3.2. Axial Energy Characteristics of Fuel Rod #H3T

Axial Cumulative number of fissions Maxi- Energy deposition

coordi- at axial interval (fiss) mum at infinite time*

nate power of

from U235 U23

1 Pu29 Pu241 Other Total fuel rod cal/g J/g per- lower Xof 10-13 X10. X10.3 X103 iso- xl0"13 (kW) fuel fuel unit3 ) end of topes I3.35s fuel rod X1010

(mm) _t__ _

10.0

15.0

20.0')

25.0

30.0

35.0

40.0

45.0

50.0

55.0

60.0

65.0

70.0

75.0

80.0

85.0

0.000

0.000

1.500

2.510

2.510

3.530

3.500

3.560

3.550

3.660

3.700

3.750

3.750

3.600

3.540

3.440

90.0

95.0

100.0

105.0

110.0

115.0

120.0

125.0

130.0

135.0

140.0

145.0

150.0

155.0

160.0

165.0

170.0

175.02)

180.0

185.0

3.440

3.370

3.420

3.380

3.370

3.360

3.340

3.330

3.350

3.380

3.430

3.430

3.450

3.630

2.720

2.720

2.720

1.090

0.000

0.000

0.000

0.000

3.330

5.550

5.550

8.710

8.590

8.440

8.430

8.510

8.620

8.760

8.800

8.620

8.510

8.440

8.470

8.520

8.680

8.750

8.730

8.680

8.650

8.690

8.760

8.840

8.940

9.020

9.030

9.180

6.900

6.900

6.900

2.760

0.000

0.000

0.000

0.000

2.350

3.920

3.920

5.360

5.280

5.180

5.170

5.210

5.280

5370

5.390

5.290

5.220

5.190

5.210

5.260

5.360

5.410

5.390

5.370

5.340

5.370

5.410

5.460

5.530

5.580

5.580

5.660

4.310

4.310

4310

1.720

0.000

0.000

0.000

0.000

0.974

1.620

1.620

2.200

2.170

2.110

2.100

2.110

2.130

2.170

2.180

2.160

2.130

2.130

2.140

2.180

2.220

2.260

2.250

2.240

2.230

2.250

2.260

2.290

2.320

2.340

2.330

2.350

1.790

1.790

1.790

0.715

0.000

0.000

0.000

0.000

1.710

2.850

2.850

4.300

4.280

4.270

4.250

4.250

4.240

4.240

4.240

4.230

4.230

4.230

4.230

4.230

4.230

4.230

4.230

4.230

4.230

4.230

4.230

4.230

4.230

4.220

4.220

4.210

3.430

3.430

3.430

1.370

0.000

0.000

0.000

0.000

4.860

8.110

8.110

11.20

11.00

10.90

10.90

11.10

11.20

11.40

11.40

11.10

11.00

10.90

10.90

10.90

11.10

11.10

11.10

11.10

11.00

11.00

11.10

11.20

11.40

11.40

11.50

-11.70

8.890

8.890

8.890

3.560

0.000

0.000

0.000

0.000

1.270

2.120

2.120

2.920

2.880

.-2.850

2.850

2.890

2.920

2.970

2.980

2.910

2.870

2.830

2.840

2.840

2.890

2.910

2.900

2.890

2.870

2.880

2.900

2.930

2.970

2.990

2.990

3.060

2.320

2.320

2.320

0.928

0.000

0.000

0.000

0.000

413.0

413.0

413.0

387.0

388.0

393.0

393.0

397.0

397.0

396.0

395.0

392.0

391.0

388.0

387.0

383.0

382.0

379.0

379.0

379.0

379.0

377.0

377.0

377.0

377.0

377.0

377.0

382.0

356.0

356.0

356.0

356.0

0.000

0.000

0.000

0.000

1729.

1729.

1729.

1620.

1624.

1645.

1645.

1662.

1662.

1658.

1653.

1641.

1637.

1624.

1620.

1603.

1599.

1586.

1586.

1586.

1586.

1578.

1578.

1578.

1578.

1578.

1578.

1599.

1490.

1490.

1490.

1490.

0.000

0.000

0.00

0.00

1.00

1.00

1.00

0.94

0.94

0.95

0.95

0.96

0.96

0.96

0.96

0.95

0.95

0.94

0.94

0.93

0.92

0.92

0.92

0.92

0.92

0.91

0.91

0.91

0.91

0.91

0.91

0.92

0.86

0.86

0.86

0.86

0.00

0.00 I

All numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate * 2.5 mm

1) Initial coordinate of fuel is 19.5 mm

2) End coordinate of fuel is 174.5 mm

3) Current value per maximum value

G-50
#H3T ý(p W I a-, jreirraiat .ed Clad .din tmd-e~iGRTcsts-'

Table G-3.3. Radial Energy Characteristics of Fuel Rod #H3T

Coordinates of fuel zones (mm)

Characteristics* I zone 2 zone 3 zone 4 zone

1.2-2.811 2.811-3.432 3.432-3.704 3.704-3.790

Number of fissions x 10- 4 (fiss) 4.430 2.600 1.270 0.414

Power of fuel rod') (kW) 11.40 6.660 3.260 1.060

U235 Energy deposition 2

) (cal/g fuel) 120.0 117.0 115.0 112.0

Energy deposition2

) (J/g fuel) 502.0 490.0 481.0 469.0

Energy deposition3) (per-unit) 1.000 0.975 0.958 0.933

Number of fissions xI0"-2 (fiss) 11.40 6.440 2.970 0.896

Power of fuel rod') (kW) 0.289 0.163 0.075 0.023

U238 Energy deposition2

) (cal/g fuel) 3.060 2.870 2.650 2.400

Energy deposition2) (J/g fuel) 12.80 12.00 11.10 10.00

Energy deposition3) (per-unit) 1.000 0.938 0.866 0.784

Number of fissions x10-" (fiss) 5.560 3.780 2.590 1.460

Power of fuel rod') (kW) 14.70 9.990 6.850 3.870

Pu2 39 Energy deposition2) (cal/g fuel) 156.0 177.0 242.0 411.0

Energy deposition2) (J/g fuel) 653.0 741.0 1013. 1720.

Energy deposition3) (per-unit) 0.380 0.431 0.589 1.000

Number of fissions xI-0"3 (fiss) 21.90 15.60 11.20 6.650

Power of fuel rod') (kW) 5.700 4.050 2.900 1.730

Pu24t Energy deposition 2

) (cal/g fuel) 60.40 71.40 102.0 183.0

Energy deposition 2

) (J/g fuel) 253.0 299.0 427.0 766.0

Energy deposition3) (per-unit) 0.330 0.390 0.557 1.000

Number of fissions x 10" (fiss) 4.930 3.040 1.770 0.844

Other Power of fuel rod') (kW) 0.013 0.008 0.005 0.002

isoto- Energy deposition2) (cal/g fuel) 0.137 0.141 0.164 0.235

pes Energy deposition2) (J/g fuel) 0.570 0.590 0.690 0.980

Energy deposition 3

) (per-unit) 0.583 0.600 0.698 1.000

Number of fissions x 10"'4 (fiss) 12.30 8.000 5.010 2.560

Power of fuel rod') (kW) 32.10 20.90 13.10 6.680

Total Energy deposition 2) (cal/g fuel) 340.0 369.0 462.0 708.0

Energy deposition2 ) (J/g fuel) 1423. 1545. 1934. 2964.

Energy deposition3) (per-unit) 0.480 0.521 0.653 1.000

1) at time of 3.35 s, 2) at infinite time, 3) Current value per maximum value.

* All numerical values of characteristics were calculated for undamaged part of fuel stack only (See Table C.2.1.)

G-51
#H3T

,. I ~ Fuel R~dsc:i~ ~.i

~ _ d Cladding) undcr lGR~TeSs; -I

Table G-3.4. Fuel Enthalpy Vs. Time Calculated by FRAP-T6 Code for Fuel Rod #H3T I

Enthalpy at fuel radius 1) Energy deposition Timefuel) Fuel enthFue yin fuel rod

(s) 1.20 mm 2.82 mm 3.47 mm 3.79 mm caVg fuel J/g fuel cag fuel Jig fuel

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

32

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

3.16

14.9

19.5

25.7

35.5

52.1

82.0

131

196

251

270

0.00

3.09

14.3

18.4

24.0

32.7

48.1

75.1

121

179

228

256

0.00

2.92

13.1

16.3

20.6

27.5

38.1

56.0

86.5

131

171

201

0.00

2.72

11.7

14.0

17.0

21.9

24.0

31.6

50.9

73.2

130

150

0.00

3.05

14.1

18.0

23.4

31.8

45.7

70.4

112

167

216

245

0.00

12.8

58.9

75.4

97.9

133

191

295

470

702

907

1027

0.00

3.21

15.7

20.5

27.2

37.5

54.9

85.9

137

203

260

296

318

331

339

344

348

351

353

354

356

357

358

360

361

363

364

367

376

0.00

13.4

65.6

85.7

.114

157

230

360

574

850

1088

1242

1332

1387

1421

1443

1458

1469

.1478

1484

1490

1495

1499

1508

1514

1520

1524

1538

1577 ____ I I L _____ .L _____ I J.

Radial enthalpy distribution and fuel enthalpy are presented at elevation 273 mm

Maxiimum value of fuel enthalpy is 251.6 caVg fuel (t=3.89 s)

1) All nmuerical values are presented at elevation vith peak pover

G-52
#H3T

Table G-3.5. Energy Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel

Rod #H3T

SEnergy of Cad-to-coolant heat

Time de in r Fuel enthalpyt) metal-water Leakage of energy') transfer coefflcient

(s) depgsitifnu) Power 1) (callg fuel) reaction') (cal/g fuel) t k W/mK)

(cal/g fuel) (kW/m) (calle fuel) _______K

IIRA-.T6 ISCANlR FRAP-T6 FRAP-T6 SCANAIR FRAP-T6 I SCANA

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

3.41

16.6

21.7

28.9

39.8

58.4

91.3

145

216

276

315

338

352

361

366

370

373

375

377

378

380

381

383

'385

386

387

391

400

0.00

12.3

39.8

53.2

77.7

125

220

387

584

633

446

266

156

94.6

60.2

40.2

28.2

20.5

16.3

13.8

11.8

10.2

8.95

6.66

524

4.33

3.71

-2.59

0.36

0.00

3.05

14.1

18.0

23.4

31.8

45.7

70.4

112

167

216

245

0.00

2.92

14.0

17.4

22.9

31.7

44.2

69.6

111

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.01

0.08

0.00

0.00

0.80

1.95

3.71

6.30

10.7

19.3

32.1

37.2

42.9

50.6

0.00

0.01

0.93

1.98

3.76

6.49

10.2

18.1

30.8

0.00

0.03

2.82

4.23

6.07

8.50

16.8

24.5

16.9

1.76

2.29

2.46

0.00

0.10

3.15

4.42

6.40

9.65

14.7

26.8

0.,91

___________ S S. A. A. S I a a.

")All nunerical values arprm• seted at elevation iith peak povr

G-53
#H3T 1 (PreirrAdi1u M dd Cladding 6derlGR"Tests :

Table G-3.6. Temperature Variation, Fission Gas Release and ZrO2 Thickness Vs. Time for Fuel

Rod #H3T Calculated by FRAP-T6 and SCANAIR Codes

Fuel centerline Fuel surface Clad outer Average Time 1) Fission gas release ZrO2

2)

(s) temperature) temperature) temperatu1) (%) thickness

(K) SN(K) (K) [SS)

FRAP-T6 ISEANAIR IFRAP-T6 ISCANAMIR FRAP-6 SCANIR I FRAP-T6 SCANAIR IFRAP-T6

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

347

529

594

684

818

1042

1430

2024

2626

3002

3113

293

341

517

573

661

796

984

1360

1961

293

340

480

515

559

629

659

765

1025

1317

2004

2223

293

336

479

514

566

641

732

836

998

293

315

394

398

403

409

422

432

500

975

1242

1324

293

313

385

387

390

395

401

412

629

0.00

0.10

0.23

0.29

0.38

0.56

0.92

1.93

3.89

7.96

14.4

26.8

0.00

0.34

1.23

1.57

1.95

2A4

2.76

3.20

3.61

5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.02

5.10

1 All nwnerical values are presented at elevation %ith peak po%1r

2) Initial ZrO2 thickness is 5 tIn

G-54
#H3T i d C . -eristics rCddersiidual of Rcfabricated Fuel Rods

I (reiradat~y~,reiradated Cladding) under GRTests

Table G-3.7. Mechanical Characteristics of Fuel Rod #1H3T Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes

Clad outer Fuel hoop Fuel - clad gap Clad hoop Clad hoop Internal gas (s)i temperature ) strainr) width' strain1) stress]) pressure

(K) (%) (mm) %(MPa) (MPa)

FRAP-T6JSCANAIR FRAP-T61SCANAII FRAP.T61SCANAI FRAP-T61SCANAIR FRAP-T61SCANAIR FRAP.T61SCANAIF

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

315

394

398

403

409

422

432

500

975

1242

1324

293

313

385

387

390

395

401

412

629

0.00

0.10

0.36

0.45

0.58

0.78

1.12

1.77

2.90

4.50

5.58

6.77

0.00

0.03

0.16

0.19

0.26

0.36

0.52

0.88

1.79

0.03

0.03

0.02

0.02

0.01

0.00

0.00

0.00

0.00

0.00

0.32

0.28

0.03 1 0.01

0.03

0.03

0.03-

0.02

0.02

0.02

0:00

0.00

0.02

0.08

0.09

0.09

0.10

0.29

0.83

1.76

3;13

12.6

12.7

0.01

0.02

0.08

0.09

0.10

0.11

0.12

0.17

0.86

8.29

8.50

8.99

9.10

9.24

9.42

212

293

93.7

78.9

0.00

0.00

8.02

8.28

9.03

9.26

9.59

10.1

10.7

12.2

311

1.70

1.74

1.83

1.85

1.88

1.91

1.96

2.01

2.08

2.19

0.10

0.10

1.70

1.74

1.84

1.87

1.90

1.93

1.97

2.01

2.04

J. ______ J. J. ______ J. J.A. J.

1) All numerical values are presented at elevation %ith peak poi.r

G-55
#H3T iindividual Charadce fcs of Refabricated Fuel Rods

(Preirradiated Fuel hadiated Cladding) under IGR Tests ,

Table G-3.8. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #H3T

Axial interval Energy deposition at infinite time Fuel enthalpy

from-to at time (t=4.26 s)

(mm)-(mm) cal/g fuel J/g fuel per-unit cal/g fuel J/g fuel per-unit

19.5-35.0 409 1713 1.00 261 1092 1.00

35.0-50.5 390 1636 0.96 249 1043 0.96

50.5-66.0 396 1660 0.97 253 1058 0.97

66.0-81.5 393 1647 0.96 250 1050 0.96

81.5-97.0 386 1619 0.95 246 1032 0.95

97.0-112.5 380 1593 0.93 242 1015 0.93

112.5 - 128.0 378 1585 0.93 241 1010 0.93

128.0 - 143.5 377 1580 0.92 240 1007 0.92

143.5 - 159.0 376 1577 0.92 240 1005 0.92

159.0- 174.5 356 1492 0.87 227 951 0.87

450

400

-350

• 300

- 250

200

: 150

100 *oo

w50

0

0 30 60 90 120 150

Axial coordinate (mm)

180

Fig. G-3.6. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6 Code

for Fuel Rod #H3T

G-56
#H3T (ndMdul. qerstics of Refabricated Fuel Rods

I(Preirradiatt_,k Preirradiated Cladding) under IGR Tests'

1.2

U235

E

0

0

I

1.0

0.8

0.6

0.4

ý4I

3

II

0.2 I I i

I 2 3 4

Radial fuel coordinate (mm)

1.2

pu2

a, 4)

~

0

'0

I

~L1

1.0

0.8

0.6

0.4

.4 4

-4- 4

V

I -~

0.2 -f- I

1 2 3 4

Radial fuel coordinate (mm)

Fig. G-3.7. U235 and Pu239 Radial Distributions of Energy Deposition for Fuel Rod #H3T

G-57
#H3T individual CharactlýTesof Refabricated Fuel Rods

[(Preirridiated Fue1ffirMrdiated Cladding) under IGR Tests

1.2

U,

~

0

U,

0

1.0

0.8

0.6

0.4

4

.... 4

4- II II

0.2-

1 2 3 4

Radial fuel coordinate (mm)

90

80

70

_ 60

950

40

W 30

20

10

0

-@- 2.Os

--O-a-- 3.0Os

- 6 - -

1.0 1.5 2.0 2.5 3.0 3.5 4.0

Radial fuel coordinate (mm)

Fig. G-3.8. Radial Distributions of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #H3T

G-58
#H3T SIndividual •Cqtcristics of Refabricated Fuel Rods

(Prvrradiated Cladding) Under IGR Tests.

800

600

0

• 400

200

/I • FRAP-T6

Power of fuel rod

-40-- Energy deposition

-a3- Fuel enthalpy

- Leakage of energy

• Clad oxidation energy

400

300 ":

200.

200 .

0

I

0 t - S ? ~ f

0 2 3 4 5 6 7 8 9 10

Time (s)

3500

3000

2500

2000

E" 1500

1000

500

0

35

30

0

25 U

S..

20

1o

.0

10

*0

4.~E

5

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. G-3.9. Energy and Temperature Characteristics Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes for Fuel Rod #H3T

G-59
#H3T individual Ch6ýa-tenRsfdcsof Refabricated Fuel Rods (Preirradiatid Fueitreafraiated Cladding) unider IGR Tests

2.5

2.0

io 1.5'

I-. Co 1.0'

E

0.5

0.0.

15

12

I

0 1 2 3 4 5 6 7 8 9 10

Time (s)

500

400

300

.o

0

0

200 -

U

100

0

0.35

0.28

E

0.21 -S

cc

to

0.14 .

U

0.07

0.00

a

C9

6

3

0

0 1 2 3 4 5 6 :7 8 9 10

Time (s)

Fig. G-3.10. Cladding Mechanical Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #H3T

G-60
.#H3T I Indivlduatid iictristics of Refabricated Fuel Rods " I

S(P.eirradit el. Preirradiated Cladding) under IGR Tests:

25

20

0

0

-. 010

oL

3500

2800

2100

.E.E

U

1400 C

700

0

5

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

*0

C

0)

0)

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. G-3.11. Fuel Strain and Fission Gas Release Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #1H3T

G-61
#H3 T fIndividual ChMarat'itcs of Refabricated Fuel Rods _ _ _ _ _ _ _ _

I(Preirradiated Fue WTrradiated Cladding) under IGR Tests

Table G-3.9. Some Results of PIE for Fuel Rod #O13T

Characteristic Value

I Measured parameters of cladding oxidation and cladding

deformation

1.1 Cladding thickness at elevation 80, 55, 130 mm correspondent to

different azimuthal angles (tim):

00 691 - R

900 677 - 663

1860 691 - 663

2700 287 640 653

1.2 ZrO2 thickness at elevation 80, 55, 130 mm correspondent to

different azimuthal angles (pm):

00 28 35 60

900 20 75 .10

1800 25 105 10

2700 23 43 53

1.3 aZr(O) thickness at elevation 80, 55, 130 mm correspondent to

different azimuthal angles (pm):

00 30 24 40

900 20 60 8

1800 25 60 10

2700 27 35 35

1.4 Clad hoop strain at elevation 80, 55, 130 mm, respectively (%) 8.6 - -

2 Measured parameters for FGR analysis

2.1 Internal gas composition (% by volume):

He

N2

02

Ar

CO2

Kr

Xe

2.2 Free gas volume (cm3

)

2.3 Gas pressure inside fuel rod under normal condition (MPa)

2.4 Kr concentration in fuel (cm 3

/g fuel)

3 Measured parameters of cladding hydriding

3.1 Coefficient of hydride orientation (per-unit) I3.2 Hydrogen concentration (% by weight)

G-62
#H3T Individrizdaacteristics of Refabricated Fuel Rods'

(PreiriadihQ-.Fuel, Preirradiated Cladding) under IGR Tests."

Table G-3.10. General Characteristic of Fuel Rod. #113T

Parameter Unit Value

Experiment FRAP-T6 SCANAIR

1 Type of coolant -- water water water

2 Bunmup MWd/kg U 49.3 49.3 49.3

3 Energy deposition in fuel rod cal/g fuel 384 384 384

4 Peak fuel enthalpy caVg fuel - -

5 Peak fuel temperature K - -

6 Peak clad temperature K - -

7 Fuel rod failure Yes, No Yes Yes -

8 Type of failure:

- cladding rupture due to ballooning Yes, No Yes Yes -

- cladding rupture due to PCMI Yes, No No No -

- fragmentation of fuel rod Yes, No No --

9 Failure time s - 3.58 -

10 Fuel enthalpy at failure cal/g fuel - 212

11 Outer cladding temperature at failure K - 1237

12 Internal gas pressure at failure MPa - 2.33

13 ZrO2 thickness after test Pm 10-105 5.10

14 Residual clad hoop strain:

- peak value for ballooning area % - -

- other location1) % 8.6 -

15 Kr concentration in internal gas % by volume - -

composition after test

16 Xe concentration in internal gas % by volume - - composition after test

17 Kr concentration in fuel after test cm3/g fuel - -

"Calculated values by FRAP-T6 and SCANAIR codes are average along height of fuel rod excluding ballooning region

G-63

G-65
#H4T Individual Charactensti s ofRefabricated Fuel Rods'

• (Preirradiated Fue'fW idiated Cladding) under IGR Tests

4)

4)

C

U.)

4)

0

lI Ii Axial coordinate (mm)

Fig. G4.1. Appearance of Fuel Rod #114T (photographs and X-ray photograph) and Profilometry

G-66
#H4T I IndividualMacteristics of Refabricated Fuel Rods ', _-,-': I I (Preirrad~~1, Preirradiated Cladding) under IGR Tests .1

Position I

Fig. G-4.2. Cross-Section and Cladding Microstructure for Fuel Rod #114T at 90 mm Elevation

G-67
ftH4T ___ ___ ___ ___ ___ __

Fig. G-4.3. Fuel Microstructure for Fuel Rod #H14T at 90 mm Elevation

G-68
#H4T Ig nd:~dj~~ceitc fRfliae ulRd:

Table G-4.1. Time Dependent Energy Characteristics of Fuel Rod #H4T

Reac- Cumulative number of fissions Power Energy

tor in fuel rod (fiss) of fuel deposition

Time energy rod in fuel rod

(s) deposi- u235 U 2 38 P23 9 P 2 4' Oter Total (kW)

1)on U2 5 Other Tota cal/g Jig fuel tin) x10"1 xI0"13 xl10-14 XI014 iso- xl0"14 fuel

topes

X10.11

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4.

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

9.0

10.0

20.0

30.0

0o

0.000

0.739

3.340

4.180

5.230

6.610

8.590

11.80

17.30

27.20

42.70

60.00

73.30

81.20

85.50

87.90

89.50

90.60

91.40

92.10

92.70

93.30

93.80

94.80

95.40

95.90

96.20

96.70

97.10

98.60

99.10

100.0

0.000

0.039

0.178

0.223

0.279

0.353

0.459

0.628

0.923

1.450

2.280

3.200

3.910

4.330

4.560

4.690

4.780

4.830

4.880

4.920

4.950

4.980

5.000

5.060

5.090

5.120

5.130

5.160

5.180

5.260

5.290

5.340

0.000

0.010

0.043

0.054

0.068

0.086

0.111

0.152

0.224

0.352

0.553

0.777

0.949

1.050

1.110

1.140

1.160

1.170

1.180

1.190

1.200

1.210

1.210

1.230

1.240

1.240

1.250

1.250

1.260

1.280

1.280

1.300

0.000

0.059

0.264

0.331

0.414

0.523

0.680

0.931

1.370

2.150

3.380

4.750

5.800

6.420

6.760

6.960

7.080

7.170

7.230

7.290

7.340

7.380

7.420

7.500

7.550

7.590

7.610

7.650

7.690

7.810

7.840

7.910

0.000

0.024

0.108

0.136

0.170

0.214

0.279

0.382

0.561

0.883

1.390

1.950

2.380

2.630

2.770

2.850

2.900

2.940

0.000

0.046

0.210

0.262

0.328

0.415

0.539

0.738

1.090

1.710

2.680

3.770

4.600

5.090

5.360

5.520

5.620

5.680

5.740

5.780

5.820

5.850

15.880

5.950

5.990

6.020

6.040

6.070

6.100

6.190

-6.220

6.280

0.000

0.123

0.555

0.695

0.869

1.100

1.430

1.960

2.880

4.530

7.100

9.980

12.20

13.50

14.20

14.60

14.90

15.10

15.20

15.30

15.40

15.50

15.60

15.80

15.90

15.90

16.00

16.10

16.20

16.40

16.50

16.60

0.000'

0.749

1.830

2.220

2.820

3.860

5.820

9.720

17.50

30.40

42.00

38.10

24.80

13.80

7.690

4.650

3.150

2.360

1.920

1.650

1.470

1.330

1.220

0.828

0.578

0.430

0.339

0.276

0.208

0.048

0.024

0.000

0.000

1.410

6.360

7.970

9.960

12.60

16.40

22.40

33.00

51.80

81.30

114.0

140.0

155.0

163.0

168.0

171.0

173.0

175.0

176.0

177.0

179.0

180.0

182.0

183.0

184.0

185.0

186.0

187.0

191.0

192.0

196.0

0.000

5.900

26.60

33.40

41.70

52.70

68.70

93.80

138.0

217.0

340.0

477.0

586.0

649.0

682.0

703.0

716.0

724.0

733.0

737.0

741.0

749.0

753.0

762.0

766.0

770.0

774.0

779.0

783.0

800.0

804.0

820.0

2.970

2.990

3.010

3.030

3.040

3.080

3.100

3.110

3.120

3.140

3.150

3.200

3.220

3.250

Maximum value of power is 42.7 kW (t - 3.65 s).

1) Current energy deposition per maximum energy deposition (at infinite time)

G-69
#H4T I~~~~~~R To6eanaedFc ~s.nii ~~~ Cla~~~~ ddn)ndrGR es l

Table G-4.2. Axial Energy Characteristics of Fuel Rod #H4T

Axial Cumulative number of fissions Maxi- Energy deposition

coordi- at axial interval (fiss) mum at infinite time*

nate power of

from u2S U23

1 Pu23 9 Pu24' Other Total fuel rod cal/g J/g perlower xi13 x 10 x10"'13 x 10"-3 iso- x 13 (W) fuel fuel unit)

end of topes t=3.65s

fuel rod xlxW ul

(mm) xl0._°

10.011

15.0

20.0

25.0

30.0

35.0

40.0

45.0

50.0

55.0

60.0

65.0

70.0

75.0

80.0

85.0

90.0

95.0

100.0

105.0

110.0

115.0

120.0

125.0

130.0

135.0

140.0

145.0

150.0

155.0

160.0

165.02)

170.0

175.0

180.0

185.0

0.189

0.947

0.947

0.947

2.050

2.000

1.940

1.880

1.830

1.820

1.810

1.810

1.810

1.880

1.920

1.920

1.870

1.830

1.820

1.840

1.840

1.840

1.820

1.750

1.700

1.670

1.660

1.640

1.630

1.670

1.750

1.330

0.000

0.000

0.000

0.000

0.393

1.970

1.970

1.970

4.840

4.770

4.630

4.540

4.440

4.390

4.370

4.400

4.420

4.490

4.560

4.560

4.460

4.430

4.420

4.450

4.450

4.480

4.490

4.420

4.340

4.290

4.250

4.210

4.210

4.220

4.370

3.340

0.000

0.000

0.000

0.000

0.292

1.A60

1.A60

1A60

2.960

2.940

2.870

2.830

2.770

2.730

2.720

2.730

2.730

2.740

2.760

2.750

2.670

2.640

2.630

2.630

2.610

2.630

2.630

2.600

2.560

2.540

2.520

2.510

2.530

2.540

2.650

2.060

0.000

0.000

0.000

0.000

0.121

0.605

0.605

0.605

1.220

1.210

1.180

1.170

1.150

1.130

1.120

1.120

1.120

1.110

1.120

1.110

1.080

1.070

1.070

1.060

1.060

1.070

1.070

1.070

1.060

1.050

1.040

1.040

1.050

1.050

1.090

0.854

0.000

0.000

0.000

0.000

0.200

0.999

0.999

0.999

2.330

2.320

2.260

2.240

2.200

2.160

2.140

2.160

2.170

2.160

2.180

2.170

2.110

2.110

2.110

2.100

2.090

2.120

2.120

2.120

2.090

2.080

2.070

2.060

2.070

2.060

2.130

1.660

0.000

0.000

0.000

0.000

0.607

3.030

3.030

3.030

6.280

6.200

6.040

5.920

5.790

5.720

5.690

5.700

5.710

5.780

5.850

5.820

5.670

5.600

5.570

5.580

5.560

5.580

5.570

5.470

5.370'

5.300

5.270

5.230

5.250

5.300

5.530

4.270

0.000

0.000

0.000

0.000

0.156

0.779

0.779

0.779

1.610

1.590

1.550

1.520

1.490

1.470

1.460

1.460

1.460

1.480

1.500

1.490

1.450

1.440

1.430

1.430

1.430

1.430

1.430

1.400

1.380

1.360

1.350

1.340

1.350

1.360

1.420

1.100

0.000

0.000

0.000

0.000

'219.0

219.0

219.0

219.0

213.0

210.0

208.0

205.0

202.0

.201.0

199.0

197.0

196.0

196.0

195.0

194.0

193.0

191.0

190.0

190.0

190.0

189.0

189.0

188.0

187.0

188.0

188.0

189.0

190.0

192.0

194.0

194.0

0.000

0.000

0.000

0.000

917.0

917.0

917.0

917.0

892.0

879.0

871.0

858.0

846.0

841.0

833.0

825.0

820.0

820.0

816.0

812.0

808.0

800.0

795.0

795.0

795.0

791.0

791.0

787.0

783.0

787.0

787.0

791.0

795.0

804.0

812.0

812.0

0.000

0.000

0.000

0.000

1.00

1.00

1.00

.1.00

0.97

0.96

0.95

0.94

0.92

0.92

0.91

0.90

0.89

0.89

0.89

0.89

0.88

0.87

0.87

0.87

0.87

0.86

0.86

0.86

0.85

0.86

0.86

0.86

0.87

0.88

0.89

0.89

0.00

0.00

0.00

0.00

All numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate ± 2.5 mm

)Initial coordinate of fuel is 11.5 nun

2) End coordinate of fuel is 166.5 mm

3) Current value per maximum value

G-70
#H4T J nWdi liirtia efbiae uiRs.

e. iralai ýCidl - er] t ii

Table G-4.3. Radial Energy Characteristics of Fuel Rod #H4T

Coordinates of fuel zones (mm)

Characteristics* 1 zone 2 zone 3 zone 4 zone

1.2-2.811 2.811-3.432 3.432-3.704 3.704-3.790

Number of fissions x10"14 (fiss) 2.560 1.500 0.735 0.239

Power of fuel rod') (kW) 6.440 3.780 1.850 0.603

U235 Energy deposition2) (callg fuel) 62.50 61.10 59.90 58.50

Energy deposition2) (J/g fuel) 262.0 256.0 251.0 245.0

Energy deposition3) (per-unit) 1.000 0.978 0.958 0.936

Number of fissions x 10"12 (fiss) 6.490 3.650 1.680 0.508

Power of fuel rod') (kW) 0.161 0.091 0.042 0.013

U235 Energy deposition2) (cal/g fuel) 1.560 1.470 1.350 1.220

Energy deposition2 ) (J/g fuel) 6.530 6.150 5.650 5.110

Energy deposition3) (per-unit) 1.000 0.942 0.865 0.782

Number of fissions x 10"14 (fiss) 3.090 2.100 1.440 0.816

Power of fuel rod') (kW) 8.040 5.460 3.750 2.120

Put39 Energy deposition2 ) (cal/g fuel) 78.10 88.50 •121.0 206.0

Energy deposition2

O (J/g fuel) 327.0 370.0 507.0 862.0

Energy deposition3) (per-unit) 0.379 0.430 0.587 1.000

Number of fissions x10"43 (fass) 12.10 8.580 6.160 3.670

Power of fuel rod') (kW) 3.090 2.200 1.580 0.941

Pu241 Energy deposition 2

) (cal/g fuel) 30.10 35.60 51.10 91.40

Energy deposition 2

) (J/g fuel) 126.0 149.0 214.0 383.0

Energy deposition3) (per-unit) 0.329 0.389 0.559 1.000

Number of fissions xl0"Wi (fiss) 2.780 1.710 0.997 0.475

Other Power of fuel rod') (kW) 0.007 0.004 0.003 0.001

isoto- Energy deposition 2

) (cal/g fuel) 0.069 0.071 0.083 0.119

pes Energy deposition2 ) (J/g fuel) 0.290 0.300 0.350 0.500

Energy deposition3 ) (per-unit) 0.584 0.599 0.698 1.000

Number of fissions x 10-14 (fiss) 6.920 4.500 2.810 1.430

Power of fuel rod') (kW) 17.70 11.50 7.220 3.680

Total Energy deposition2

? (cal/g fuel) 172.0 187.0 234.0 358.0

Energy deposition (J/g fuel) 720.0 783.0 980.0 1499.

Energy deposition3

) (per-unit) 0.480 0.522 0.654 1.000

I at time of3.65 s, 2) at infinite time. 3) Current value per maximum value.

* All numerical values of characteristics were calculated for undamaged part offuel stack only (See Table C.2.1.)

G-71
#H4T I ] L edCladding) undr lGRTests,

Table G-4.4. Fuel Enthalpy Vs. Time Calculated by FRAP-T6 Code for Fuel Rod #H4T

Enthalpy at fuel radius F 1) Energy deposition

Time (a fEll fu el Fuel in fuel rod

(S) 1.20 mm 2.82 mn 3.47 mm 3.79n ca/g fuel J/g fuel cafuel Jig fuel

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

42

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

1.41

6.06

7.54

9.36

11.8

152

20.6

30.0

47.1

74.8

108

137

151

157

159

159

156

152

146

141

134

128

113

99.6

88.2

78.5

52.5

7.77

0.00

1.39

5.84

7.26

9.01

11.3

14.5

19.4

28.3

44.3

69.1

97.3

118

121

118

112

104

98.3

93.4

88.9

85.0

81.7

78.9

72.9

67.4

62.3

57.7

42.7

7.55

0.00

1.33

5.51

6.85

8.49

10.5

13.1

17.2

24.6

34.9

50.7

66.3

71.8

67.6

64.1

58.9

56.0

55.9

53.9

52.3

51.7

51.3

50.9

49.9

48.3

46.3

44.2

35.5

7.36

0.00

125

5.19

6.44

7.95

9.60

11.6

14.6

20.0

22.1

29.0

34.5

35.2

38.9

33.6

32.5

36.4

37.0

36.0

36.4

37.3

38.1

38.8

39.6

39.4

38.7

37.6

31.6

7.24

0.00

1.38

5.80

7.21

8.94

11.2

14.2

19.0

27.5

41.7

64.4

89.9

.108

114

113

111

107

103

99.4

95.5

9i .9

88.5

85.4

78.1

71.3

65.3

59.9

43.5

7.56

0.00

5.78

24.3

30.2

37.5

46.8

59.6

79.7

115

175

270

377

455

477

475

.463

448

433

417

400

385

371

358

327

299

274

251

182

31.7

0.00

1.32

6.15

7.72

9.65

12.2

15.7

21.3

31.0

48.4

76.5

110

140

155

163

167

171

173

175

176

177

179

180

182

183

184

185

187

192

0.00

5.54

25.8

32.3

40A

51.0

65.9

89.4

130

203

321

460

586

649

684

702

715

725

732

738

744

748

753

762

767

772

775

784

806 ________ I A. ________ A. A. I I

Radial enthalpy distribution and fuel enthalpy are presented at elevation 19.3 mm

Maximum value of fuel enthalpy is 114.5 cal/g fuel (t=425 s)

1) All numerical values are presented at elevation N'ith peak pomr

G-72
#H4T I u'el~r~irradiated o Rea Claddractin uni Rods 

W(if ueýTefjeiiradiaied Cladding) under'JOR Tests'-'-j

Table G-4.5. Energy Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel

Rod #H4T

Time Energy Linear F n ) Ener Lakage of energy') Clad-to-coolant heat

Timed tio power,) Fuel enthalpy' metal-ter Leaagotransfer coefficient')

( s itn;fuel) (kW/m) (caYg fuel) reaction'1 (cal/g fuel) (kW/m2K) (s_____u_ FRkW/m) SCANAIR F(caP/ fuel)

nwA-T6 IscANAR FRAp-T6 FRA-T6 scANAmIR nRA-T6 scm

0.0

1.0

2.0

2.2

2A

2.6

2.8

3.0

3.2

3A

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

1.47

6.86

8.60

10.7

13.5

17.5

23.8

34.6

53.9

85.2

122

156

173

182

187

190

193

195

196

198

199

200

202

204

205

206

208

214

0.00

5.68

14.0

16.9

21.3

28.8

42.8

70.5

126

222

321

311

195

108

60.4

39.2

26.1

19.3

15.5

13.2

11.7

10.6

9.73

6.66

4.63

3.44

2.70

1.65

0.20

0.00

1.38

5.80

7.21

8.94

11.2

14.2

19.0

27.5

41.7

64.4

89.9

108

114

113

III

107

103

99.4

95.5

91.9

88.5

85.4

78.1

71.3

65.3

59.9

43.5

7.56

0.00

1.32

5.87

7.15

9.00

11.4

14.4

19.7

29.5

44.1

,68.8

92.5

105

108

106

100

94.9

88.6

83.1

77.4

72.3

68.4

64.2

55.2

47.7

40.8

34.9

19.7

5.43

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00-0

0.00

0.00

0.00

0.02

0.02

0.09

0.51

1.29

2.59

4.67

9.17

17.6

29.5

45.2

58.3

68.6

77.1

85.3

91.4

97.4

103

108

112

116

125

133

140

146

164

0.00

0.00

0.05

0.07

0.12

0.60

1.34

2.70

5.08

8.75

16.9

30.7

44.3

59.0

70.0

81.3

89.8

98.8

106

114

120

126

131

143

152

160

167

185

205

0.00

0.03

0.03

0.03

0.79

1.94

3.10

4.76

7.40

16.6

232

28.7

29A

25A

23.8

21.0

15A

14.9

14.5

13.0

11.7

10.8

10.1

8.79

7.76

6.92

6.22

4.30

0.29

0.00

0.10

0.10

0.10

0.73

2.19

3.29

5.25

8.99

15.0

26.9

32.6

28.6

322

28.6

25.5

233

21.3

19.7

18.4

16.5

152

14.0

11.9

102

8.77

7.53

4.07

0.00 1 205 0.10 J. ______ ± _____ J. a j. _____ _____ a.

1) All numerical values are presented at elevation %&ith peak pow

G-73
#H4T pri '~~dCadn)tdiG ct

Table G-4.6. Temperature Variation, Fission Gas Release and ZrO2 Thickness Vs. Time for Fuel

Rod #H4T Calculated by FRAP-T6 and SCANAIR Codes

Time Fuel centerline Fuel surface Clad outer Fission gas release Average ZrO2

2 ) (s) temperature1) temperature temperature (%) thickness

(K) (K) (K) Nt me

FRAP-T6 SCANAIR FRAP-T6 I SCANAIR FRAP-T6 =SCANAIR FRAP-T6 SCANAIR FRAP-T6

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

318

394

417

446

482

532

610

743

975

1338

1750

2085

2230

2294

2313

2307

2281

2239

2185

2123

2056

1986

1812

1650

1508

1385

1048

421

293

315

389

409

438

477

523

607

754

968

1342

1743

2004

2154

2211

2229

2217

2179

2126

2054

1971

1894

1800

1569

1367

1182

1028

668

380

293

315

380

400

424

449

479

524

602

631

729

805

814

865

793

778

831

840

825

831

844

854

863

874

872

862

847

765

413

293

313

378

396

422

451

483

540

632

740

828

852

854

810

769

729

702

675

655

637

634

635

634

627

615

599

580

503

378

293

304

352

368

384

390

395

400

406

422

430

436

437

433

431

428

420

420

419

417

415

413

412

409

407

405

404

398

379

293

302

348

361

378

383

385

388

394

401

412'

423

440

4i7

414

4n11

409

407

406

404

402

401

400

397

395

393

392

386

375

0.00

0.08

0.16

0.19

0.22

0.27

0.34

0.45

0.65

1.06

1.89

3.34

4.90

6.69

9.18

9.59

9.89

9.97

9.98

9.99

10.0

10.0

10.0

10.1

10.1

10.1

10.1

10.1

10.1

0.00

0.17

0.61

0.71

0.84

0.99

1.26

1.76

2.23

2.68

3.20

3.43

3.50

4.39

4.75

5.15

5.41

5.60

5.68

5.70

5.69

5.67

5.64

5.56

5.48

5.39

5.29

4.89

4.08

5

'5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

11 All nnmerical values are presented at elevation with peak power

2) Initial ZzOz thickness is 5 pn

G-74
#H4T I t ~nd~hi1Ch ti~sofefatrifcked FýeI odi~: ~~~ ~ iruidCladdinij) t& 6der'GRTst.

Table G-4.7. Mechanical Characteristics of Fuel Rod #H4T Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes

Clad outer Fuel hoop Fuel - clad gap Clad hoop Clad hoop Internal gas Time temperature1) strain') width') strain) stress') pressure (s) W N (mm) (%) (MPa) (MPa)

FRAP-T6IS FRAP-T61SCAN FRAP-T61SCAN FR-T61SC FRAP-T6ISCANAER FRAP-T6ISCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

293

304

352

368

384

390

395

400

406

422

430

436

437

433

431

428

420

420

419

417

415

413

412

293

302

348

361

378

383

385

388

394

401

412

423

440

417

414

411

409

407

406

404

402

401

400

397

395

393

392

386

375

0.00

0.04

0.17

0.21

0.26

0.33

0.41

0.55

0.78

1.18

1.80

2.52

3.12

3.67

3.83

3.76

3.66

3.47

328

3.08

2.90

2.73

2.58

0.00 1 0.03 0.03

0.01

0.07

0.08

0.10

0.13

0.16

0.22

0.34

0.52

0.86

1.28

1.69

1.86

1.82

1.73

1.64

1.54

1.45

1.36

1.28

1.22

1.16

1.03

0.93

0.84

0.76

0.58

0.03

0.02

0.02

0.02

0.02

0.02

0.01

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.01

0.01

0.02

0.03

0.03

0.04

0.05

0.06

0.07

0.08

0.10

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.02

0.02

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.01

0.01

0.02

0.02

0.02

0.03

0.01

0.02

0.05

0.06

0.07

0.08

0.08

0.09

0.10

0.38

0.88

1.45

1.91

.2.34

2.50

2.43

2.32

2.32

2.32

2.31

2.31

2.31

2.30

2.30

2.30

2.29

2.29

2.28

0.01

0.01

0.05

0.06

0.07

0.08

0.08

0.09

0.10

0.13

0.17

0.44

0.78

0.91

0.88

0.80

'0.72

0.64

0.56

0.49

0.48

0.47

0.47

0.46

0.46

0A5

0.45

0.43

8.59

8.68

8.93

8.99

9.06

9.14

9.24

9.38

9.56

329

424

404

283

11.4

182

143

11.7

11.7

11.7

11.6

11.6

11.5

11.5

11.4

11.3

11.2

11.1

10.8

8.02

8.14

8.45

8.52

8.63

8.81

9.01

9.35

9.91

10.7

12.1

288

399

410

383

302

224

134

50.9

11.6

11.4

11.3

11.1

10.9

10.7

10.5

10.3

9.71

1.70

1.72

1.76

1.77

1.79

1.80

1.82

1.85

1.88

1.93

1.97

2.01

2.04

2.09

2.13

2.13

2.14

2.14

2.13

2.12

2.12

2.11

2.10

2.08

2.06

2.05

2.03

1.99

1.70

1.72

1.77

1.78

1.80

1.82

1.84

1.87

1.91

1.95

1.99

2.01

2.02

2.04

2.05

2.06

2.07

2.07

2.07

2.07

2.07

2.06

2.06

2.05

2.03

2.02

2.01

1.95

6.5

7.0

7.5

8.0

10.0

30.0

409

407

405

404

398

379

2.23

1.93

1.67

1.46

0.94

0.08 0.42 0.13 0.03 2.26 1 0.42 9.94 8.88 1 1.83 1 1.85 I

") All nuncrical valucs are prccntcd at elevation with peak povxr

G-75
#H4T I Ch'E~ii~~cfaricaed ]ndvrd~ Fel Ros 

'

(ie e M Claddinig) ufiderlIGR Tests~

Table G-4.8. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #H4T

Axial interval

from-to

(mm)-(mm)

Energy deposition at infinite time Fuel enthalpy

at time (t=4.25 s)

calg fuel J/g fuel per-unit cal&g fuel J/g fuel per-unit .4 4. .4 4 4 +

11.5-27.0

27.0 - 42.5

42.5 - 58.0

58.0-73.5

73.5 - 89.0

89.0 - 104.5

104.5 - 120.0

120.0- 135.5

135.5 - 151.0

151.0- 166.5

219

210

202

195

194

191

189

187

188

191

917

879

845

818

811

800

790

783

787

802

1.00

0.96

0.92

0.89

0.88

0.87

0.86

0.85

0.86

0.87

114

110

105

102

101

99.8

98.'6

97.7

98.2

100

480

460

442

428

424

418

413

410

412

419

1.00

0.96

0.92

0.89

0.88

0.87

0.86

0.85

0.86

0.87

250

200

U

150

C)

- 100

0

In.

O)

~50

0

0 20 40 60 80 100

Axial coordinate (mrm)

120 140 160 180

Fig. G-4.4. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6 Code

for Fuel Rod #H4T

G-76
#H4T 1~diiI'CltiiiadicsU of Refabricte FueIo% '0&

4)4

1.2

0.8

0 0.6 Ii

0

S 0.4

0.2

2 3 4

Radial fuel coordinate (mum)

1.2-

_____ _____ ____ ____pun

1.0

, 0.8

U.ZS

0.6

,.5.

-I

t

P.1 0.4 i= I• .. ::"-••-

0.22

12 3 4

Radial fuel coordinate (mm)

Fig. G-4.5. U235 and Pu23 Radial Distributions of Fission Number for Fuel Rod #H4T

G-77
#H4T 1sidivi~uafCliiracteni~~Refabricatei1 Fuel Rods.

I (Preii~ad~ j~j~~irradiated Claddizig) ider~lGRTests~ I

1.2

0

1.0

0.8

0.6

0.4

0.2

1

1

1

Radial fuel coordinate (mm)

1.0 1.5 2.0 2.5 3.0 3.5 .4.0

Radial fuel coordinate (mm).

Fig. G-4.6. Radial Distributions of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #H4T

G-78
#H4T I lndividuat'arteristics of Refabricated Fuel Rods

I(Preirrad . , Preirradiated Cladding) under IGR Tests

350

280

- 210

1.4

O 140

0

250

- An

70

0

2500

2000

,- 1500

E 1000

500

01

0 1 2 3 4 5 6 7 8 9 10

Time (s)

•UU

U

150

0.

U

100 "

U

50

*0

35

0

28 .

U

0

U

21

.0-7

14

7

0

0 1 2 3 4 5

Time (s)

6 7 8 9 10

Fig. G-4.7. Energy and Temperature Characteristics Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes for Fuel Rod #H4T

G-79
#H4T I.IndividUai Chir-'az csofRefabricated Fuel Rods

(Preirradiated Fu[,t%ý.ri.idiated Cladding) under IGR Tests

2.5

2.0

0G

2 1.5

.a.

-- 1.0

E

0.5

0.0

3.0

2.5

2.0

.-q

a, 1.

5

0

0

U 1.0

0.5

0.0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

600

480

360

U

240 ."

*0

120

0

0.12

0.10

i

0.08 2

.5

0.06

CU

0.04 ";

0.02

0.00

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. G-4.8. Cladding Mechanical Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #H4T

G-80
#H4T IndividuadC acteristics of Refabricated Fuel Rods I (Preirrad j'~el, Preirradiated Cladding) under IGR Tests

0

0

T

3.)

2500

2000

1500

1000

5O00

0 1 2 3 4 5 6 7 8 9 10

Time (s)

12

10

0

C..)

0

4.)

U.

8

6

4

2

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. G-4.9. Fuel Strain and Fission Gas Release Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #H4T

G-81
#tH4T ,Individual Chacra' nftds of Refabricated Fuel Rods

[ (Preirradited F e dmiated Cladding) under IGR Tests

Table G-4.9. Some Results of PIE for Fuel Rod #114T

Characteristic Value

1. Measured parameters of cladding oxidation and cladding

deformation

1.1. Cladding thickness at elevation 90 mm for different azimuthal

angles (pm):

00 700

900 691

1800 700

2700 705

1.2. ZrO2 thickness at elevation 80, 55, 130 mm for different azimuthal

angles (pm):

00 5

900 5

1800 5

2700 5

1.3. aZr(O) thickness at elevation 80, 55, 130 mm for different

azimuthal angles (pm):

00 0

900 0

1800 0

2700 0

1.4. Clad hoop strain at elevation 80, 55, 130 mm (%) 0

2. Measured parameters for FGR analysis

2.1. Internal gas composition (% by volume):

He 89.06

N2 0.17

02 0.03

Ar 0.01

CO2 0.01

Kr 1.01

Xe 9.71

2.2. Free gas volume (cm 3

) 5.98

2.3. Gas pressure inside fuel rod under normal condition (MPa) 1.768

2.4. Kr concentration in fuel (cm 3

/g fuel) 0.13

3. Measured parameters of cladding hydriding

3.1. Coefficient of hydride orientation (per-unit)

3.2. Hydrogen concentration (% by weight) 5.5 10-3

G-82
#H4T I individuidPGr "ieris'tics of Refabricated Fuel Rods:':

V(Preinidi•,•tFl Preirradiated Cladding) uider IGR Tests

Table G-4.10. General Characteristic of Fuel Rod #H4T

Parameter Unit Value

Experiment FRAP-T6 SCANAIR

I Type of coolant - water water water

2 Burnup MWd/kg U 48.7 48.7 48.7

3 Energy deposition in fuel rod cal/g fuel 196 196 196

4 Peak fuel enthalpy calg fuel - 114 108

5 Peak fuel temperature K - 2313 2229

6 Peak clad temperature K - 437 440

7 Fuel rod failure Yes, No No No

8 Type of failure:

- cladding rupture due to ballooning Yes, No No No -

- cladding rupture due to PCMI Yes, No No No -

- fragmentation of fuel rod Yes, No No - -

9 Failure time .s - -

10 Fuel enthalpy at failure cal/g fuel - -

11 Outer cladding temperature at failure K - -

12 Internal gas pressure at failure MPa - - -

13 ZrO2 thickness after test Pm 5 5 -

14 Residual clad hoop strain:

- peak value for ballooning area % - - -

- other location) % 0 1.68 0

Kr concentration in internal gas % by volume 1.01 1.34 0.59

composition after test

Xe concentration in internal gas % by volume 9.71 8.06 3.51

16 composition after test % byvolume_9.71_8.06_3.5

17 Kr concentration in fuel after test cm3/g fuel 0.13 0.15 0.19

"Calculated values by FRAP-T6 and SCANAIR codes are average along height or fuel rod excluding ballooning region

G-83

.fi.divid Ial

APPENDE

acteristics fior FW M5 under iGR Test

G-85
#H5T Individual ChheibradeAi of Refabricated Fuel Rods I(Preiiradiated Fue "-rdiated Cladding) under IGR Tests I

Positionfi (0)

Fig. G-5.1. Appearance of Fuel Rod #H5T (photographs and X-ray photograph)

G-86 '
#H5T I 'ndividual.iaric~erstics of Refabricated Fuel Rods

Trei eirradiated Cladding) under IGR Tests::i

Pocitinn 1

Pnqitinn2

Fig. G-5.2. Cross-Section and Cladding Microstructure for Fuel Rod #115T at 40 mm Elevation

G-87
aFuel Rods "

#H5T I(Pi" dba iiTi ed Cladding)kndcr IGR Tests

Fig. G-5.3. Cross-Section and Cladding Microstructure for Fuel Rod #HST at 85 mm Elevation

G-88
#H5T i r cst of Refa~ric;a Fuel Rods - IPre d _ePreirmadiated Cladding) under IGR Testis

-f *01

N I

2.1

Fig. G-5.4. Fuel Microstructure for Fuel Rod #H5T at 85 mm Elevation

G-89
#H5T :Idi~rd~w , Mncfadbriae FnlR

I(Prer~m ~ d~ Cladding) udcirGRTess.

Table G-5.1. Time Dependent Energy Characteristics of Fuel Rod #HST

Reac- Cumulative number of fissions Power Energy

tor in fuel rod (fiss) of fuel deposition

Time energy rod in fuel rod

(s) deposi- u235 U23

s Pu. 9 Pu241 Other Total (k"' cal/g J/g fuel

tion) x10"1 xI0"13 xl0"14 XI0"14 iso- X10"14 fuel

(%) topes

x10"11

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

9.0

10.0

20.0

30.0

Co

0.000

0.620

4.740

6.840

9.790

14.00

20.10

29.10

42.20

59.20

73.50

82.00

86.80

89.60

91.40

92.60

93.50

94.10

94.60

95.00

95.30

95.60

95.90

96.30

96.70

96.90

97.20

97.50

97.80

99.10

99.60

100.0

0.000

0.038

0.290

0.418

0.598

0.855

1.230

1.780

2.580

3.620

4.490

5.010

5.300

5.480

5.590

5.660

5.710

5.750

5.780

5.810

5.830

5.840

5.860

5.880

5.910

5.920

5.940

5.960

5.980

6.060

6.080

6.130

0.000

0.009

0.069

0.099

0.142

0.203

0.291

0.421

0.610

0.857

1.060

1.190

1.260

1.300

1.320

1.340

1.350

1.360

1.370

1.380

1.380

1.380

1.390

1.390

1.400

1.400

1.410

1.410

1.420

1.440

1.440

1.450

0.000

0.057

0.436

0.628

0.900

1.290

1.850

2.670

3.870

5.440

6.760

7.540

7.980

8.240

8.400

8.510

8.590

8.650

8.700

8.730

8.760

8.790

8.810

8.850

8.880

8.910

8.930

8.960

8.990

9.110

9.150

9.230

0.000

0.023

0.180

0.259

0.370

0.530

0.761

1.100

1.590

2.240

2.780

3.100

3.280

3.390

3.460

3.500

3.540

3.560

3.580

3.600

3.610

3.620

3.630

3.640

3.660

3.670

3.680

3.690

3.700

3.750

.3.770

3.800

0.000

0.045

0.343

0.493

0.707

1.010

1.A50

2.100

3.040

4.270

5.310

5.920

6.260

6.470

6.600

6.690

6.750

6.800

6.830

6.860

6.880

6.900

6.920

6.950

6.980

7.000

7.010

7.040

7.060

7.150

7.190

7.250

0.000

0.119

0.913

1.310

1.880

2.690

3.870

5.590

8.110

11.40

14.10

15.80

16.70

17.20

17.60

17.80

18.00

18.10

18.20

18.30

18.30

18.40

18.40

18.50

18.60

18.60

18.70

18.80

18.80

19.10

19.10

19.30

0.000

0.778

4.830

6.810

9.660

13.90

20.20

29.80

42.70

47.60

30.80

17.30

10.10

6.250

4.150

2.920

2.160

1.660

1.290

1.090

0.930

0.802

0.699

0.517

0.406

0.334

0.285

0.246

0.198

0.052

0.027

0.000

0.000

1.502

11.55

16.59

23.73

34.02

48.83

70.56

102.3

143.9

178.5

199.5

211.1

218.4

222.6

225.8

227.9

228.9

231.0

232.1

233.1

233.1

234.2

235.2

236.3

237.3

238.4

239.4

240.5

244.7

245.7

251.0

0.000

6.293

48.39

69.51

99.43

142.5

204.6

295.6

428.6

602.9

747.9

835.9

884.5

915.1

932.7

946.1

954.9

959.1

967.9

972.5

976.7

976.7

981.3

985.5

990.1

994.3

998.9

1003

1008

1025

1029

1052

Maximum value orpower is 49.0 kW (t - 3.35 s).

1) Current energy deposition per maximum energy deposition (at infinite time)

G-90
#H5T I~~~~S ftc~~falbiica±&1 Rl~dlf~i Fiel R66s. I ? ~~rerrdia~dClddig~undr GRTet

Table G-5.2. Axial Energy Characteristics of Fuel Rod #HST

Axial Cumulative number of fissions Maxi- Energy deposition

coordi- at axial interval (fiss) mum at infinite time*

nate power of

from U235 U2.. Pu239 Pu24' Other Total fuel rod cal/g J/g perlower x10.13 xl0-11 xI0.13 xIO13 iso- x10"13 (kW) fuel fuel unit3)

end of topes t=335s

fuel rod topes0 t}3.J5

(mm) xI 0.10

10.0

15.0

20.0

25.0')

30.0

35.0

40.0

45.0

50.0

55.0

60.0

65.0

70.0

75.0

80.0

85.0

90.0

95.0

100.0

105.0

110.0

115.0

120.0

125.0

130.0

135.0

140.0

145.0

150.0

155.0

160.0

165.0

170.0

175.0

180.02)

185.0

0.000

0.000

0.000

1.700

1.890

1.890

1.890

2.480

2.580

2.520

2.370

2.210

1.520

1.520

1.520

1.520

2.370

2.290

2.150

2.090

1.990

1.980

1.970

2.020

2.110

2.080

1.990

2.040

2.130

2.200

1.470

1.470

1.470

1.470

0.440

0.000

0.000

0.000

0.000

3.250

3.610

3.610

3.610

5.330

5.510

5.430

5.230

4.940

3.660

3.660

3.660

3.660

5.570

5.520

5.470

5.420

5.380

5.370

5.390

5.370

5.300

5.360

5.450

5.430

5.410

5.450

3.320

3.320

3.320

3.320

0.996

0.000

0.000

0.000

0.000

2.450

2.730

2.730

2.730

3.470

3.590

3.530

3.400

3.210

2.270

2.270

2.270

2.270

3.480

3.410

3.320

3.260

3.180

3.180

3.180

3.200

3.230

3.230

3.210

3.230

3.280

3 .330

2.240

2.240

2.240

2.240

0.673

0.000

0.000

0.000

0.000

1.000

1.120

1.120

1.120

1.400

1.450

1.430

1.380

1.310

0.933

0.933

0.933

0.933

1.420

1.400

1.370

1.350

1.330

1.330

1.330

1.330

1.330

1.340

1.350

1.350

1.360

1.370

0.924

0.924

0.924

0.924

0.277

0.000

0.000

0.000

0.000

1.700

1.880

1.880

1.880'

2.600

2.590

2.580

2.570

2.570

1.820

1.820

1.820

1.820

2.640

2.670

2.700

2.710

2.720

2.710

2.700

2.690

2.680

2.670

2.660

2.660

2.670

2.690

1.710

1.710

1.710

1.710

0.512

0.000

0.000

0.000

0.000

5.200

5.770

5.770

5.770

7.410

7.680

7.540

7.200

6.780

4.760

4.760

4.760

4.760

7.330

7.160

6.900

6.760

6.560

6.540

6.540

6.610

6.730

6.710

.6.600

6.680

6.820

6.970

4.670

4.670

4.670

4.670

1.400

0.000

0.000

0.000

0.000

1.320

1.470

1.470

1.470

1.880

1.950

1.910

1.830

1.720

1.210

1.210

1.210

1.210

1.860

1.820

1.750

1.720

1.670

1.660

1.660

1.680

1.710

1.700

1.680

1.700

1.730

1.770

1.180

1.180

1.180

1.180

0.355

0.000

0.000

0.000

0.000

283.4

283.4

283.4

283.4

248.9

248.9

248.9

246.8

246.8

247.9

247.9

247.9

247.9

251.0

250.0

245.8

244.7

241.6

241.6

240.5

242.6

246.8

244.7

240.5

242.6

245.8

247.9

247.9

247.9

247.9

247.9

247.9

0.000

0.000

0.000

0.000

1187

1187

1187

1187

1043

1043

1043

1034

1034

1039

1039

1039

1039

1052

1048

1030

1025

1012

1012

1008

1016

1034

1025

1008

1016

1030

1039

1039

1039

1039

1039

1039

0.000

0.00

0.00

0.00

1.00

1.00

1.00

1.00

0.88

0.88

0.88

0.87

0.87.

0.87

0.87

0.87

0.87

0.89

0.88

0.87

0.86

0.85

0.85

0.85

0.86

0.87

0.86

0.85

0.86

0.87

0.87

0.87

0.87

0.87

0.87

0.87

0.00

All numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate . 2.5 mm

I)nitial coordinate of fuel is 23.0 mm

2) End coordinate of fuel is 179.0 mm

3) Current value per maximum value

G-91
#H5T I ~ (Pre~ra4~j~~ed Refabricated Cladding) Fuel under Rods~ IGR Tests ~>II

Table G-5.3. Radial Energy Characteristics of Fuel Rod #HST

Coordinates of fuel zones (mm)

Characteristics* I zone 2 zone 3 zone 4 zone

1.2 - 2.811 2.811-3.432 3.432-3.704 3.704-3.790

Number of fissions x10" (fiss) 2.207 1.297 0.634 0.206

Power of fuel rod') (kW) 5.512 3.232 1.579 0.515

U235 Energy deposition2

O (callg fuel) 77.60 75.82 74.25 72.48

Energy deposition2 ) (J/g fuel) 325.3 316.9 310.6 303.3

Energy deposition 3

) (per-unit) 1.000 0.977 0.957 0.934

Number of fissions x 10"2 (fiss) 5.627 3.169 1.464 0.441

Power of fuel rod1) (kW) 0.138 0.078 0.036 0.010

U238 Energy deposition 2

) (cal/g fuel) 1.945 1.830 1.684 1.527

Energy deposition2 ) (J/g fuel) 8.147 7.666 7.049 6.390

Energy deposition3) (per-unit) 1.000 0.941 0.866 0.785

Number of fissions x10"'4 (fiss) 2.730 1.851 .1.276 0.720

Power of fuel rod') (kW) 7.028 4.779 3.273 1.851

Pu239 Energy deposition2) (cal/g fuel) 99.35 113.0 153.7 261.5

Energy deposition2

) (J/g fuel) 416.2 472.7 643.2 1095

Energy deposition3

) (per-unit) 0.380 0.432 0.588 1.000

Number of fissions x10"t3 (fiss) 10.77 7.635 5.470 3.263

Power of fuel rod') (kW) 2.730 1.935 1.391 0.825

Pu24' Energy deposition2) (cal/g fuel) 38.38 45.39 65.05 116.1

Energy deposition2

) (J/g fuel) 161.1 190.3 271.9 486.3

Energy deposition 3

) (per-unit) 0.331 0.391 0.560 1.000

Number of fissions x10"n (fiss) 2.458 1.516 0.884 0.420

Other Power of fuel rod') (kW) 0.006 0.004 0.002 0.001

isoto- Energy deposition 2

) (cal/g fuel) 0.089 -0.091 0.106 0.152

pes Energy deposition 2

) (J/g fuel) 0.366 0.377 0.439 0.638

Energy deposition 3

) (per-unit) 0.583 '0.599 0.697 1.000

Number of fissions X 10-14 (fiss) 6.066 3.943 2.479 1.265

Power of fuel rod') (kW) 15.37 10.02 6.285 3.211

Total Energy deposition 2

) (callg fuel) 217.5 235.3 296.0 452.8

Energy deposition 2

) (J/g fuel) 910.9 985.2 1239 1896

Energy deposition3

) (per-unit) 0.480 '0.520 0.654 1.000

I) at time of 3.35 s. 2) at infmrite time, 3) Current value per maximum value.

0 All numerical values of characteristics were calculated for undamaged part of fuel stack only (See Table C.2.1.)

G-92
#H5T haratcnsicsoRefabirkced Fiuel Rds<-66

Table G-5.4. Fuel Enthalpy Vs. Time Calculated by FRAP-T6 Code for Fuel Rod #1H5T

1rIme Enthalpy at fuel radius Fuel lMp Energy deposition

Time _ (ca/ fuel) F in fuel rod

(s) 1.20mm 1282 mm 13.47 mm 1 3.79 mrn cal/g fuel IJ/g fwe clg fuel Jig fuel

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

32

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

1.60

12.0

17.4

24.9

35.5

50.0

73.6

107

149

185

204

215

220

222

221

219

217

213

209

.205

200

195

180

164

150

137

98.9

17.2

0.00

1.58

11.7

16.9

23.8

33.5

46.6

66.7

952

132

160

174

178

178

176

173

169

163

156

.149

142

137

132

121

113

106

99.8

79.7

16.5

0.00

1.51

11.0

15.5

21.0

28.6

36.9

47.7

67.5

89.3

113

122

126

130

129

126

118

109

101

96.2

93.1

90.8

88.9

85.3

82.3

79.5

76.8

66.3

15.8

0.00

1.43

10.1

13.7

17.6

22.8

23.5

27.7

36.7

47.5

71.7

88.6

942

104

102

96.7

85.4

76.8

71.9

70.7

70.1

69.8

69.6

69.0

68.2

67.2

65.9

0.00

1.56

11.5

16.5

23.1

32.4

44.1

623

89.2

123

152

167

173

176

176

173

168

163

157

152

i47

142

138

128

.19

111

104

0.00

6.55

48.3

69.3

97.0

136

185

261

374

514

638

699

725

738

736

725

705

681

657

635

615

596

578

537

500

466

436

341

69.1

0.00

1.50

11.5

16.7

24.0

34.3

48.3

71.2

103

144

179

199

211

218

222

225

228

229

231

232

233

233

234

235

236

237

238

240

246

0.00

630

48.2

70.1

100

144

203

298

432

604

749

833

884

913

932

945

954

961

966

971

974

978

980

986

990

993

996

1005

1030

59.4

15.4

81.4

16.5 J. I I

Radial enthalpy distribution and fuel enthalpy are presented at elevation 30.8 mm

Ma.'dnum value of fuel enthalpy is 176.2 cal/g fuel (t=--4.26 s)

) All nwuerical values are presented at elevation %%ith peak povr

G-93
#H5T IlindivaiWuafC"V rrsitrRfby ie FuelRd

(Prtn!goid Cladding) under IGR4 Tests ]

Table G-5.5. Energy Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel

Rod #H5T

Energy Linear Energy of Clad-to-coolant heat

Tim depositionmeoe' Fuel enthalpy') metal-water Leakage of energy') transfer coefficienti)

s t(cag fuel) (kW/m) (calg fuel) reactioni) (cal/g fuel) (kW/m2K)

(s__ a_ fue____ F(AP6m)P-- (j AP fuel) " - S FRAP-T6 ISC7ANI, FRAP-T6 FRAW-T6 ISCANAIR IFRAP-T6 ISCANATR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

1.70

13.0

18.9

27.1

38.7

54.6

80A

117

163

202

225

238

246

251

255

257

259

260

262

263

264

264

266

267

268

269

271

278

0.00

7.20

44.7

63.6

902

130

185

278

398

439

283

161

93.1

57.5

38.2

26.9

19.9

15.3

11.9

10.1

8.59

7A1

6.45

4.78

3.75

3.09

2.64

1.83

0.25

0.00

1.56

11.5

16.5

23.1

32.4

44.1

62.3

89.2

123

152

167

173

176

176

173

168

163

157

152

147

142

138

128

119

111

104

81.4

16.5

0.00

1,.45

11.3

15.5

22.1

31.3

42.4

60.5

86.1

114

142

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.01

0.02

0.02

0.02

0.02

0.02

0.02

0.02

0.02

0.02

0.02

0.02

0.02

0.02

0.02

0.02

0.00

0.00

0.09

0.91

2.55

5.16

9.37

17.8

28.4

39.3

42.3

"47.2

53.6

60.1

67.5

80.5

95.4

108

117

124

130

136

141

152

161

170

177

201

273

-0.00

0.00

0.12

0.84

2.48

5.22

8.91

15.8

27.5

38.0

40.9

0.00

0.03

1.24

3.74

6.14

8.83

16.5

22.0

27.1

4.79

1.81

2.10

2.26

2.18

3.66

7.30

11.7

20.4

17.6

15.6

14.3

132

12.4

10.7

9.55

8.63

7.87

5.65

0.79

0.00

0.10

1.31

3.73

627

9.77

14.1

21.9

33.4

0.96

1.56

"All nmnaical values ar presented at elevation vith peak powzr

G-94
#H5T~ ~ y ijrrrdiaied Claddinig) under MGR Tst

Table G-5.6. Temperature Variation, Fission Gas Release and ZrO2 Thickness Vs. Time for Fuel

Rod #H5T Calculated by FRAP-T6 and SCANAIR Codes

Average

Fuel centerline Fuel surface Clad outer A r

Tim temperature 1) 1) Fission gas release ZrO 2

2)

(s) e temperature temperature (%) thickness (K) ([) (K) (R mA)

FRA-T6 ISCANAMIR FRAP-T6 ISCANAIR IFRAP-T6 =SCANAIR IFRAP-T6 ISCANAIR IFRAN-T6

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

321

485

564

671

819

1014

1323

1738

2211

2538

2694

2772

2806

2816

2813

2801

2783

2759

2731

2699

2661

2619

2497

2360

. 2219

2082

.1642

562

293

317

472

537

640

785

956

1237

1644

2064

2427

293

318

457

510

567

642

652

711

835

981

1299

1514

1584

1710

1681

1614

1473

1364

1301

1285

1278

1274

1271

1264

1253

1240

1223

1138

535

293

315

451

499

564

641

715

796

845

977

1290

293

304

387

397

403

409

422

429

435

648

1002

1146

1224

1184

1126

945,

661

478

423

421

419

417

416

413

411

409

407

402

384

293

303

380

386

390

395

400

408

418

656

1085

0.00

0.05

0.14

0.20

0.29

0.45

0.72

1.30

2.43

4.03

6.20

8.49

12.1

16.6

18.3

18.3

18.4

18.4

18.4

18.4

18.4

18.4

18.4

18.4

18.5

18.5

18.5

18.5

18.5

0.00

0.19

0.99

1.32

1.85

2.37

2.74

3.13

3.40

3.73

5.67

5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.01

5.04

5.07

5.09

5.10

5.10

5.10

5.10

5.10

5.10

5.10

5.10

5.10

5.10

5.10

5.10

5.10

5.10

J

-z ~*l. ________ .L I I

1) Al numerical values are presented at elevation with peak pOw~r

2) Initial Z-O2 thickness is 5 pzm

G-95
#H5T I md ~ u~ham j~ii~F~fRefabiicaied Fuel ujider R~s' lGRTestsT~] 2

Table G-5.7. Mechanical Characteristics of Fuel Rod #H5T Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes

Clad outer Fuel hoop Fuel - clad gap Clad hoop Clad hoop Internal gas Time I tan I srs~Ipesr (s) temperature) strain') width) strain) stress 1 

pressure

__(K) 00 (mm) 00) (MPa) (MPa)

FRAP-T6 SCANAIR T6 I S bI • FRAP-T6I5 CAAAII AR-T6 SCA FRAP-T6 SC AN T61SCANAIN

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

304

387

397

403

409

422

429

435

648

1002

1146

1224

1184

1126

945

661

478

423

421

419

417

416

413

411

409

407

402

384

293

303

380

386

390

395

400

408

418

656

1085

0.00

0.00

0.12

0.24

0.41

0.63

0.94

1.44

2.16

3.20

4.25

4.83

5.02

5.16

5.48

5.44

5.26

5.02

4.78

4.56

4.37

4.17

3.99

3.56

3.18

2.84

2.54.

1.46

0.00

0.00

0.02

0.13

0.18

0.25

0.36

0.49

0.74

1.13

1.95

3.48

0.02

0.03

0.02

0.02

0.01

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.02

0.13

0.12

0.12

0.13

0.14

0.15

0.16

0.16

0.17

0.18

0.20

0.21

0.22

0.23

0.28

0.34

0.03

0.03

0.03

0.03

0.02

0.02

0.02

0.01

0.00

0.00

0.00

0.01

0.02

0.07

0.08

0.09

0.10

0.30

0.70

1.30

2.14

3.07

3.51

4.10

7.61

7.78

7.76

7.57

7.44

7.39

7.39

7.38

7.38

7.38

7.37

7.37

7.37

7.37

7.36

7.34

0.01

0.02

0.08

0.09

0.09

0.11

0.12

0.15

0.31

1.00

2.14

8.76

8.86

9.33

9.48

9.65

9.83

230

483

250

275

77.1

12.3

12.9

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

8.13

8.26

8.86

9.16

9.56

10.1

10.6

11.5

165.

299

14.2

1.70

1.73

1.81

1.84

1.87

1.91

1.94

1.98

2.02

2.07

2.13

1.70

1.72

1.81

1.84

1.87

1.91

1.93

1.97

1.99

2.01

2.05

2.18

2.25

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10.

0.10

0.10

0.10

0.10

0.10

0.10

1) All numerical valucs arc presented at elevation with peak powvr

G-96
#H5T jtgrpl"ýPi'UiqwadOiated Cladding) ddr0~s~~

Table G-5.8. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #H5T

Axial interval Energy deposition at infinite time Fuel enthalpy

from-to Enrydpsto atifnietm at time (t=4.26 s)

(mm)-(mm) cal/g fuel J/g fuel per-unit cal/g fuel J/g fuel per-unit

23.0-38.6 283 1188 1.00 176 738 1.00

38.6-54.2 258 1079 0.91 160 671 0.91

54.2 -69.8 247 1037 0.87 154 645 0.87

69.8 - 85A 248 1039 0.87 154 646 0.87

85.4-101.0 249 1044 0.88 155 649 0.88

101.0- 116.6 243 1018 0.86 151 633 0.86

116.6 - 132.2 243 1019 0.86 151 633 0.86

132.2- 147.8 243 1018 0.86 151 - 633 0.86

147.8 - 163.4 247 1035 0.87 154 644 0.87

163.4 - 179.0 248 1039 0.87 154 646 0.87

300

• 250

Co

2•00

0

£; 0 150

50

. .... . . . . .n . . .. . . . . __ . . . .. __ m e n J . o -

Energy deposition

Fuel enthalpy

0

20 40 60 80 100 120 140 160 180

Axial coordinate (mm)

Fig. G-5.5. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6 Code

for Fuel Rod #HST

G-97
T [M 1acoefbiaid g)(mderjGR;cst Fe oPe~dd~tiTdld 

1.0.

0.8

0.6 II

0.4 .-

0.2--

1 2 3 4

Radial fuel coordinate (mm)

1.2

Pus'

1.0*

0.8

0.6

0

0.2-

1 2 3 4

Radial fuel coordinate (mrm)

Fig. G-5.6. U235 and Pu29 Radial Distributions of Energy Deposition for Fuel Rod #HST

G-98
#H5T I. OW ýIO of diiicda Rear ai ddi )u ilRds ý- Ij

1.2

U,

I.

0

U,

1.0

0.8

0.6

0.4

0.2

1 2 3 4

Radial fuel coordinate (mm)

250

200

= 150

. 100

1,- Os

.-- 2.0s

-0- 

3.0s

-0-- 4.3s

-II

50

0

1.0 1.5 2.0 2.5 3.0 3.5 4.0

Radial fuel coordinate (mm)

Fig. G-5.7. Radial Distributions of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #HST

G-99
#H5T AniliA es fFtee1 t Rcids 

I de ratei Cta.addh~~he G et

500

400

, 300

o 200

100 0

0,..

100

0

3000

2500

2000

1500

E

1000

500

0

300

240

180 2

120 Cd

60

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

36

d

30

U

U

0 24

U

612 

6L)

5

0

0 1 2 3 4 5 6 .7 8 9 10

Time (s)

Fig. G-5.8. Energy and Temperature Characteristics Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes for Fuel Rod #HST

G-100
#H5T [t~~iniiaiid Clidding)-ýider IGR Tests:-I

2.5.

2.0-

1.5

E

0.5.

0.0.

10

8

500

0-

"U

I

0 1 2 3 4 5 6 7 8 9 10

Time (s)

e.

0

6

4

0.30

0.24

0.18 -Z

CO

10

0.12 Z

Y

0.06

0.00

2

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. G-5.9. Cladding Mechanical Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #HST

G-101
#H5T I Tnd~v V~hii~iiT~o(Rfabricated FuelRd

i~ (x~i~ei~.aai~ d Claddig) unde-r 1GRJTst -

6.0

0

0

0

4)

3000

2500

2000

E

1500 •

1000

500

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

20

15

~L.10

5

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. G-5.10. Fuel Strain and Fission Gas Release Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #HST

G-102
#H5T Um C; ý6ý1 3 M

p laý !rel iiýd CliddiiW'ýýder 10'R'iTests

Table G-5.9. Some Results of PIE for Fuel Rod #H5T

Characteristic Value

I. Measured parameters of cladding oxidation and cladding

deformation

1.1. Cladding thickness at elevation 40, 85 mm correspondent to

different azimuthal angles (pm):

00 680 677

900 525 677

1800 485 663

2700 R 663

1.2. ZrO2 thickness at elevation 40, 85 mm correspondent to different

azimuthal angles (pM):

00 10 10

900 8 10

1800 10 10

2700 17 15

1.3. cZr(O) thickness at elevation 40, 85 mm correspondent to different

azimuthal angles (pm):

00 8 8

900 8 10

1800 10 10

2700 10 10

1.4. Clad hoop strain at elevation 40, 85 mm, respectively (%) 6.5 3.1

2. Measured parameters for FGR analysis

Internal gas composition (% by volume):

He

N 2

02

Ar

CO2

Kr

Xe

2.2. Free gas volume (cm3

)

2.3. Gas pressure inside fuel rod under normal condition (MPa)

2.4. Kr concentration in fuel (cm3

/g fuel)

3. Measured parameters of cladding hydriding

3.1. Coefficient of hydride orientation (per-unit) 0.28

3.2. Hydrogen concentration (% by weight) _

G-103
#H5T Fuel Rod~K ~-Y I ~ (Prei~dia~d~1 ?~jj~dia4cd Cl~ddixig) ~nider IUR Tests

Table G-5.10. General Characteristic of Fuel Rod #H5T

Parameter Unit Value

Experiment FRAP-T6 SCANAIR

I Type of coolant --- water water water

2 Burnup MWd/kg U 49.0 49.0 49.0

3 Energy deposition in fuel rod calfg fuel 251 251 251

4 Peak fuel enthalpy caVg fuel - 176 -

5 Peak fuel temperature K 2817 -

6 Peak clad temperature K 1224 -

7 Fuel rod failure Yes, No Yes Yes -

8 Type of failure:

- cladding rupture due to ballooning Yes, No Yes Yes -

- cladding rupture due to PCMI Yes, No No No -

- fragmentation of fuel rod Yes, No No --

9 Failure time s - 4.03 -

10 Fuel enthalpy at failure caVg fuel - 174 -

11 Ouier cladding temperature at failure K 1223 -

12 Internal gas pressure at failure MPa - 2.28 -

13 ZrO2 thickness after test pam 8-17 5.10 -

14 Residual clad hoop strain:

- peak value for ballooning area % 6.5 7.28 -

- other location') % 3.1 2.44 -

15 Kr concentration in internal gas % by volume -- 2.44

composition after test

Xe concentration in internal gas % by volume 14.60

composition after test

17 Kr concentration in fuel after test cM3/g fuel 0.14

tUCakculatcd values by FRAP-T6 and SANAIR codes arc average along height or fuel rod excluding ballooning region

G-104
4findividua'l -"(

APPEN~

ticteristics for :Ft 6T unlder IGR St

G-105
individual Char' det c-SofRefabricated Fuel Rods #H6T I (Preirradiat•d Fuel•. idiated Cladding) under IGR Tests

F

m

41

PositionW

EE

;6

Axial coordinate (mm)

Fig. G-6.1. Appearance of Fuel Rod #1I6T (photographs and X-ray photograph) and Profilometry

G-106
I Individuiat-l - cteristics of Refabricated Fuel Rods #H 6T :(Preirrada•.t •ig eI Preirradiated Cladding)under IGRTests..'[

Fig. G-6.2. Cross-Section and Cladding Microstructure for Fuel Rod #116T at 90 mm Elevation

G-107
#H6T Ii~iFJ/~~cd ladding ude IGR Thist:,

Positioni''

V2 -- -

Fig. G-6.3. Fuel Microstructure for Fuel Rod #H6T at 90 mm Elevation

G-108
#H6T I; (znai~tpe1'~Strmai~d Cadding) u'tnder- lOR-Tet

Table G-6.1. Time Dependent Energy Characteristics of Fuel Rod #H6T

Reac- Cumulative number of fissions Power Energy

tor in fuel rod (fiss) of fuel deposition

Time energy rod in fuel rod

(s) deposi- US pu239 Pu24 2 O r Total (kW)fuel

tiXnO xl0"4 - 013 Xl0"14 X t0"14 iso- Xp0e11 fuel

M topes

×lO-11

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

9.0

10.0

20.0

30.0

0o

0.000

0.697

2.790

3.380

4.040

4.800

5.710

6.860

8.440

10.90

15.00

22.40

34.60

51.10

67.20

77.90

84.00

87A0

89.40

90.80

91.70

92.50

93.10

94.30

95.10

95.70

96.10

96.70

97.10

98.60

99.10

100.0

0.000

0.022

0.087

0.106

0.126

0.150

0.179

0.215

0.264

0.340

0.470

0.700

1.080

1.600

2.100

2.440

2.630

2.730

2.800

2.840

2.870

2.890

2.910

2.950

2.980

.2.990

3.000

3.020

3.040

3.090

3.100

3.130

0.000

0.005

0.021

0.025

0.030

0.036

0.043

0.052

0.064

0.082

0.113

0.169

0.261

0.385

0.506

0.587

0.633

0.658

0.674

0.684

0.691

0.697

0.701

0.711"

0.717

0.721

0.724

0.728

0.732

0.743

0.747

0.753

0.000

0.032

0.127

0.154

0.184

0.218

0.260

0.312

0.384

0.495

0.684

1.020

1.570

2.330

3.060

3.540

3.820

3.970

4.070

4.130

4.170

4.210

4.240

4.290.

4.330

4.350

4.370

4.400

4.420

4.490

4.510

4.550

0.000

0.013

0.051

0.062

0.075

0.089

0.106

0.127

0.156

0.201

0.278

0.414

0.640

0.945

1.240

1.440

1.550

1.610

1.650

1.680

1.700

1.710

1.720

1.740

1.760

1.770

1.780

1.790

1.790

1.820

1.830

1.850

0.000

0.025

0.099

0.120

0.143

0.170

0.202

0.243

0.300

0.386

0.533

0.794

1.230

1.810

2.380

2.760

2.980

3.100

0.000

0.067

0.268

0.324

0.388

0.461

0.548

0.659

0.811

1.050

1.440

2.150

3.320

4.910

6.450

7.480

8.070

8.390

8.590

8.720

8.810

8.880

8.940

9.060

9.140

9.190

9.230

9.280

9.330

9.470

9.520

9.600

0.000

0.384

0.769

0.862

0.976

1.140

1.390

1.820

2.640

4.260

7.480

13.20

20.40

24.10

18.80

11.10

6.180

3.610

2.300

1.620

1.230

0.994

0.843

0.600

0.405

0.290

0.221

0.176

0.127

0.028

0.014

0.000

0.000

0.951

3.810

4.620

5.520

6.570

7.810

9.380

11.60

14.90

20.50

30.60

47.30

69.90

91.80

106.0

115.0

120.0

122.0

124.0.

126.0

127.0

128.0

130.0

131.0

132.0

132.0

133.0

134.0

137.0

138.0

141.0

0.000

3.980

15.90

19.30

23.10

27.50

32.70

39.30

48.60

62.40

85.80

128.0

198.0

293.0

384.0

444.0

481.0

502.0

511.0.

519.0

527.0

532.0

536.0

544.0

548.0

553.0

553.0

557.0

561.0

573.0

578.0

590.0

3.170

3.220

3.250

3.280

3.300

3.350

3.370

3.390

3.410

3.430

3.440

3.500

3.520

3.550

Maximum value of power is 24.1 kW (t - 4.20 s).

I) Current energy deposition per maximum energy deposition (at infinite time)

G-109
#H6T I ~!ndiv1dd~ ti i~~i_1itI~fRefabric~d Fuel Rod~ A X%~

~einadi~~j irauiM~d Cladding) under JOR Tests -~

Table G-6.2. Axial Energy Characteristics of Fuel Rod #H6T

Axial Cumulative number of fissions Maxi- Energy deposition

coordi- at axial interval (fiss) mum at infinite time*

nate power of

from U235 U238 Pu239 Pu24' Other Total fuel rod cal/g J/g perlower xIO.10 X10-11 xlO.13 xIO.13 iso- X10"13 (kW) fuel fuel unit3

) end of topes t-4.20s

fuel rodX0 0 (mm)×10°

10.0

15.01)

20.0

25.0

30.0

35.0

40.0

45.0

50.0

55.0

60.0

65.0

70.0

75.0

80.0

85.0

90.0

95.0

100.0

0.000

0.650

0.722

0.722

0.722

1.460

1.580

0.876

0.876

0.876

0.876

0.876

0.876

0.843

0.843

0.843

0.843

0.843

0.843

1.210

1.230

1.240

1.230

1.220

1.170

0*887

0.887

0.887

0.887

0.852

0.852

0.829

0.829

0.829

0.083

0.000

0.000

1.330

1.480

1.480

1.480

3.170

3.430

2.070

2.070

2.070

2.070

2.070

2.070

2.070

2.070

2.070

2.070

2.070

2.070

0.000

0.950

1.060

1.060

1.060

2.140

2.310

1.320

1.320

1320

1.320

1.320

1.320

1.270

1.270

1.270

1.270

1.270

1.270

1.910

1.950

1.960

1.940

1.920

1.840

1.120

1.120

1.120

1.120

1.080

1.080

1.050

1.050

1.050

0.105

0.000

0.385

0.428

0.428

0.428

0.873

0.943

0.540

0.540

0.540

0.540

0.540

0.540

0.521

0.521

0.521

0.521

0.521

0.521

0.000

0.683

0.759

0.759

0.759

1.530

1.530

1.010

1.010

1.010

1.010

1.010

1.010

0.987

0.987

0.987

0.987

0.000

2.000

2.220

2.220

2.220

4.500

4.870

2.760

2.760

2.760

2.760

2.760

2.760

2.660

2.660

2.660

2.660

0.987 2.660

0.987 2.660

0.000

0.501

0.557

0.557

0.557

1.130

1.220

0.691

0.691

0.691

0.691

0.691

0.691

0.666

0.666

0.666

0.666

0.666

0.666

0.985

1.010

1.010

1.000

S0.996

0.954

0.617

0.617

0.617

0.617

0.595

0.595

0.577

0.577

0.577

0.058

0.000

158.0

158.0

158.0

158.0

152.0

152.0

152.0

152.0

152.0

152.0

152.0

152.0

146.0

146.0

146.0

146.0

146.0

146.0

137.0

137.0

137.0

137.0

137.0

137.0

128.0

128.0

128.0

128.0

124.0

124.0

120.0

120.0

120.0

120.0

0.000

0.000

661.0

661.0

661.0

661.0

636.0

636.0

636.0

636.0

636.0

636.0

636.0

636.0

611.0

611.0

611.0

611.0

611.0

611.0

573.0

573.0

573.0

573.0

573.0

573.0

536.0

536.0

536.0

536.0

519.0

519.0

502.0

502.0

502.0

502.0

0.000

0.00

1.00

1.00

1.00

1.00

0.96

0.96

0.96

0.96

0.96

0.96

0.96

0.96

0.92

0.92

0.92

0.92

0.92

0.92

0.87

0.87

0.87

0.87

0.87

0.87

0.81

0.81

0.81

0.81

0.78

0.78

0.76

0.76

0.76

0.76

0.00

105.0

110.0

115.0

120.0

125.0

130.0

135.0

140.0

145.0

150.0

155.0

160.0

165.0

170.0

175.0

180.02)

185.0

3.040

3.150

3.220

3.250

3.270

3.190

2.200

2.200

2.200

2.200

2.150

2.150

1.910

1.910

1.910

0.191

0.000

0.785

0.802

0.810

0.804

0.798

0.765

0.438

0.438

0.438

0.438

0.422

0.422

0.410

0.410

0.410

0.041

1.540

1.550

1.560

1.560

1.560

1.570

0.930

0.930

0.930

0.930

0.899

0.899

0.848

0.848

0.848

0.085

3.930

4.020

4.040

4.010

3.970

3.810

2.470

2.470

2.470

2.470

2.380

2.380

2.310

2.310

2.310

0.231

0.000 1 0.000 0.000 1 0.000 1 0.000 I .5. 1 .5. 1 .~ I

* All numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate ± 2.5 mm

I) Initial coordinate of fuel is 13.0 mm

2) End coordinate of fuel is 178.0 mmn

3) Current value per maximum value

G-110
#H6T ~~xie~r~inaiaii IGR Tests

Table G-6.3. Radial Energy Characteristics of Fuel Rod #H6T

Coordinates of fuel zones (mm)

Characteristics* I zone 2 zone 3 zone 4 zone

1.2- 2.811 2.811-3.432 3.432-3.704 3.704-3.790

Number of fissions x10"-4 (fiss) 0.526 0.308 0.151 0.049

Power of fuel rod') (kW) 1.290 0.758 0.371 0.121

U235 Energy deposition 2

) (cal/g fuel) 43.80 42.80 41.90 40.90

Energy deposition2 ) (J/g fuel) 183.0 179.0 175.0 171.0

Energy deposition3) (per-unit) 1.000 0.977 0.957 0.934

Number of fissions x10"2 (fiss) 1.350 0.762 0.351 0.106

Power of fuel rod') (kW) 0.033 0.019 0.009 0.003

U238 Energy deposition 2

) (cal/g fuel) 1.110 1.040 0.960 0.869

Energy deposition 2

) (J/g fuel) 4.650 4.350 4.020 3.640

Energy deposition3) (per-unit) 1.000 0.937 0.865 0.783

Number of fissions x 10-1

4 (fiss) 0.663 0.451 0.309 0.175

Power of fuel rod') (kW) 1.680 1.140 0.784 0.443

Pu239 Energy deposition 2

) (cal/g fuel) 57.10 64.70 88.70 150.0

Energy deposition2) (J/g fuel) 239.0 271.0 371.0 628.0

Energy deposition3) (per-unit) 0.381 0.431 0.591 1.000

Number of fissions x10"43 (fiss) 2.610 1.850 1.330 0.791

Power of fuel rod') (kW) 0.652 0.462 0.331 0.197

Pu 24l Energy deposition2) (callg fuel) 22.10 26.20 37.50 67.00

Energy deposition2) (J/g fuel) 92.50 110.0 157.0 280.0

Energy deposition3) (per-unit) 0.330 0.391 0.560 1.000

Number of fissions x10"' (fiss) 0.578 0.356 0.208 0.099

Other Power of fetil rod') (kW) 0.001 0.001 0.001 0.000

isoto- Energy deposition2 ) (callg fuel) 0.049 0.051 0.059 0.084

pes Energy deposition2 ) (J/g fuel) 0.210 0.210 0.250 0.350

Energy deposition3) (per-unit) 0.584 0.601 0.699 1.000

Number of fissions x 10-14 (fiss) 1.460 0.950 0.596 0.304

Power of fuel rod') (kW) 3.670 2.380 1.500 0.764

Total Energy deposition2 ) (cal/g fuel) 124.0 135.0 169.0 259.0

Energy deposition2) (J/g fuel) 519.0 565.0 707.0 1084.

Energy deposition3 ) (per-unit) 0.479 0.52 1 0.653 1.000

1) at time of 4.20 s, 2)at infinite time. 3) Current value per maximum value.

* All numerical values of characteristics were calculated for undamaged part of fuel stack only (See Table C.2.2.)

G-111
#H6T

Table G-6.4. Fuel Enthalpy Vs. Time Calculated by FRAP-T6 Code for Fuel Rod 1#H6T

T Enthalpy at fuel radius F Energy deposition Time ~ ~(Sal& fuel) Fuel in fuel rod

(S) 1.20 nm~ 2.82 mn 3.47 rm 3.79 mm calfg fuel JIg fuel cal/g fuel Jig fuel

0.0

1.0

2.0

2.2

2A

2.6

2.8

3.0

3.2

3A

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5A

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

1.10

4.02

4.82

5.72

6.76

8.00

9.58

11.8

15.2

21.2

31.8

49.5

73.6

96.9

112

119

122

122

119

115

109

103

89.4

75.8

64.5

55.3

33.0

5.69

0.00

1.07

3.86

4.63

5A9

6.49

7.69

9.22

11.3

14.5

20.1

30.0

46.7

67.8

85.2

923

91.0

85.9

79.4

73.1

67.3

63.1

60.2

54.3

48.8

44.0

39.7

26.8

5.61

0.00

1.02

3.65

4.38

5.20

6.15

7.29

8.70

10.5

13.3

17.9

26.0

38.8

48.5

55.4

54.5

50.1

45.4

41.0

37A

35.5

36.4

36.0

34.4

33.2

31.6

-29.7

222

5.54

0.00 0.00

0.96

3A6

4.16

4.95

5.85

6.93

8.18

9.70

11.9

15.3

20.9

26.9

27.4

29.3

28.2

28.8

24.3

22.6

21.2

22.4

25.6

25.6

25.8

26.1

25.7

24.7

19.6

5.49

1.06

3.84

4.61

5.47

6.46

7.66

9.16

11.2

14.3

19.7

29.1

44.6

62.8

78.8

86.2

87.2

84.7

80.8

76.4

72.3

69.2 >

66.0

58.9

52.2

46.4

41.4

27.2

5.61

0.00

4.45

16.1

19.3

22.9

27.1

32.1

38.4

-46.9

60.0

82.4

122

187

263

330

361

365

"355

339

320

303

290

276

247

219

195

173

114

23.5

0.00

0.96

3.82

4.64

5.55

6.60

7.85

9.42

11.6

15.0

20.6

30.7

47.5

70.2

92.2

107

115

120

123

125

126

127

128

130

131

132

133

134

138

0.00

4.00

16.0

19A

23.3

27.6

32.9

39.5

48.6

62.7

86.5

129

199

294

386

448

483

503

515

523

529

533

537

544

549

553

556

563

580

Radial enthalpy distibution and fuel enthalpy are presented at elevation 21.3 mm

Maximum value of fuel enthalpy is 873 caVg fuel (t-4.72 s)

1) All numerical values are presented at elevation ¶vith peak PONier

G-112
#H6T .0dioiddichireics. of kifab~ricaýtiwFul Rd

~~.~i~7ciffdiaied Clidd-w-j imider IGRTstsTable G-6.5. Energy Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel

Rod #H6T

Energy Linear Fe Energy of Clad-to-coolant heat

Time Fuel enthalpy0 metal-water Leakage of energy) transfer coefficienti) ( d)p(siti fnc) P°Werm) (cal/g fuel) reactiont) (cal/g fuel) k/2K

(s) fuel) (calg (kW/m) FRAP..T(calls fuel) (k_ lm2K)

FRAP-T6 ISCANAI FRAP-T6 FRAP-T6 SCANAIR FRAP-T6 SCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5A

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

1.07

4.28

5.18

6.21

7.38

8.78

10.5

13.0

16.7

23.1

34.4

53.1

78.5

103

120

129

134

137

140

141

142

143

145

147

148

148

150

155

0.00

4.01

8.02

8.99

10.2

11.9

14.5

19.0

27.6

44.5

78.1

138

213

251

196

116

64.4

37.6

24.0

16.9

12.8

10.4

8.79

6.54

4.38

3.12

2.36

0.00

1.06

3.84

4.61

5A7

6.46

7.66

9.16

11.2

14.3

19.7

29.1

44.6

62.8

78.8

862

87.2

84.7

80.8

76.4

72.3

69.2

66.0

58.9

52.2

46.4

41.4

27.2

5.61

0.00

0.95

3.69

4.36

5.24

6.25

7.29

8.82

10.9

13.7

19.1

29.0

43.8

63.4

76.3

82.5

82.2

78.7

743

69.3

64.6

60.9

56.9

48.4

41.5

35.1

29.8

16.4

5.28

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.01

0.02

0.02

0.03

0.04

0.22

0.67

1.40

2.62

4.85

8.77

17.2

27.8

38.8

48.8

57.5

65.4

72.4

78.4

82.8

86.8

95.2

103

109

114

130

156

0.00

0.00

0.04

0.05

0.06

0.08

0.11

0.24

0.72

1.40

2.68

4.98

8.92

16.5

26.0

38.2

47.6

57.4

65.3

72.9

79.6

84.5

89.8

101

109

117

123

139

155

0.00

0.03

0.03

0.03

0.03

0.03

0.19

1.09

1.84

2.88

4.74

8.02

14.2

22.5

24.7

23.9

20.6

19.6

17.5

16.1

13.0

10.4

10.4

8.88

7.52

6.54

5.73

3.56

0.12

0.00

0.10

0.10

0.10

0.10

0.10

0.10

1.08

2.03

3.04

5.03

8.85

15.0

23.6

29.1

27.8

25.3

22.5

203

18.4

162

14.7

13.4

112

9.56

8.10

6.86

3.48

0.10

1.35

0.15 i _________ _______ i 1. 1 _______ I J _______

1) All numaical values ae Presented at elevation with peak pover

G-113
idi uelRod #H6T I - Ciajiider IGRTestsi

Table G-6.6. Temperature Variation, Fission Gas Release and ZrO2 Thickness Vs. Time for Fuel

Rod #H6T Calculated by FRAP-T6 and SCANAIR Codes

Average

Time Fuel centerline Fuel surface Clad outer Fission gas release ZrO22)

(s) temperature') temperature1) temperaturet) N thickness

FRAP-T6 SCANAIR FRAP-T6 I SCANAIR FRAP-T6 SCANAIR FRAP-T6 SCANAIR FRAP-T6

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

312

361

375

389

405

425

449

482

533

619

767

1008

1323

1617

1800

1888

1919

1913

1882

1832

1768

1694

1524

1351

1205

1085

784

388

293

309

354

365

379

395

412

435

469

513

596

745

965

1273

1518

1700

1778

1812

1806

1772

1718

1659

1582

1383

1207

1044

910

602

377

293

310

352

364

377

391

408

427

451

484

535

615

700

706

733

718

726

663

640

619

637

682

681

684

689

683

669

597

385

293

307

347

357

370

384

399

420

445

476

535

629

735

803

783

754

720

683

655

630

622

618

614

601

586

567

547

475

375

293

302

333

342

353

365

378

386

390

394

400

408

418

430

432

431

427

426

423

421

417

412

412

409

406

404

402

396

377

293

300

329

337

347

358

370

380

382

384

388

394

401

409

414

413

411

408

406

404

402

401

399

397

395

393

391

385.

373

0.00

0.00

0.02

0.02

0.03

0.03

0.04

0.05

0.06

0.08

0.11

0.18

0.35

0.74

1.24

1.57

2.03

3.40

5.12

5.22

5.25

5.27

5.28

5.29

5.30

5.30

5.31

5.33

5.40

0.00

0.12

0.43

0.49

0.57

o65

0.73

0.84

0.97

1.23

1.66

2.23

2.68

3.16

3.33

3.45

3.43

3.48

3.52

3.56

3.60

3.75

3.71

3.62

3.54

3.44

3.33

2.93

2.27

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5 ________ 1 ________ 1 1 ________ ________ 1 1

1) All numerical values are presented at elevation with peak power 2

) Initial ZrO2 thickness is 5 ann

G-114
#H6T I ivldiil-Auhiiceit of RefibriI citd -~c MT O,1S1

I a~1~jirrad~iaid C1idding unde G et

Table G-6.7. Mechanical Characteristics of Fuel Rod #H6T Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes

Time Clad outer Fuel hoop Fuel - clad gap Clad hoop Clad hoop Internal gas I (s) temperature0 strainD width') 'train') stress'. pressure ((%)) (K) NO (mm) (%) a (MPa)

FRP.-T76SCANAIMM RP-61SJCANAM FRAP-T6ISCANAU9 FRAP-T6 SC.ANAIRI FRAP-T6 ISCANAIR FRAP-T6 SCANAIM

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

302

333

342

353

365

378

386

390

394

400

408

418

430

432

431

427

426

423

421

417

412

412

409

406

404

402

396

377

293

300

329

337

347

358

370

380

382

384

388

394

401

409

414

413

411

408

406

404

402

401

399

397

395

393

391

385

373

0.00

0.05

0.11

0.13

o.14

0.17

0.19

022

027

0.34

0.45

0.66

1.02

1.51

1.97

2.24

2.46

2.71

2.84

2.67

2.48

2.29

2.12

1.78

1.49

1.26

1.08

0.67

0.16

0.00

0.01

0.04

0.05

0.06

0.07

0.08

0.10

0.12

0.15

0.21

0.33

0.52

0.78

0.96

1.08

1.10

1.06

1.00

0.92

0.85

0.79

0.73

0.61

0.52

0.45

0.38

023

0.10

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.02

0.02

0.02

0.01

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.01

0.02

0.03

0.04

0.05

0.06

0.08

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.02

0.02

0.01

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.01

0.01

0.01

0.02

0.02

0.02

0.03

0.01

0.01

0.03

0.04

0.05

0.06

0.07

0.07

0.08

0.08

0.69

0.10

0.18

0.58

0.94

1.15

1.31

1.52

1.63

1.49

1.32

1.23

1.23

1.23

122

1.22

1.22

1.21

1.19

0.01

0.01

0.03

0.04

0.05

0.06

0.07

0.08

0.08

0.08

0.09

0.10

0.12

0.15

0.17

0.27

0.29

0.25

0.20

0.14

0.13

0.12

0.12

0.11

0.11

0.10

0.10

0.08

0.07

8.50

8.56

8.72

8.75

8.79

8.83

8.88

8.93

9.00

9.09

9.21

9.38

81.7

408

405

395

132

355

447

273

97.8

10.6

.10.6

10.5

10.4

10.3

10.2

9.94

9.34

8.03

8.11

8.30

8.34

8.39

8.44

8.49

8.60

8.75

8.93

9.26

9.82

10.6

11.6

13.6

133

156

118

59.7

11.2

10.9

10.8

10.7

10.4

102

9.97

9.79

9.23

8.53

1.70

1.71

1.74

1.75

1.76

1.76

1.77

1.78

1.79

1.81

1.83

1.87

1.90

1.94

1.96

1.97

1.98

2.00

2.03

2.03

2.03

2.02

2.02

2.00

1.98

1.96

1.95

1.90

1.79

1.70

1.71

1.75

1.75

1.76

1.77

1.78

1.79

1.81

1.83

.1.86

1.89

1.93

1.96

1.98

1.99

1.99

1.99

1.99

1.99

1.99

1.99

1.99

1.97

1.96

1.95

1.93

1.88

1.80 .1. L1 I 15 i

11 All numerical values arc pr•scnted at elevation with peak po=r

G-115
#H6T I .Indi~idi~l ~ tliiii i~'ii Refabricat&l Cla~Iding) Fuel iind~r Rods IOR >'~Tests

Table G-6.8. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #H6T

Axial interval Energy deposition at infinite time Fuel enthalpy

from-to at time (t74.72 s)

(mm)-(mm) calIg fuel Jig fuel per-unit cal/g fuel J/g fuel per-unit

13.0-29.5 158 662 1.00 87.3 366 1.00

29.5-46.0 153 641 0.97 84.5 354 0.97

46.0-62.5 152 637 0.96 83.9 352 0.96

62.5 - 79.0 150 627 0.95 82.6 346 0.95

79.0-95.5 146 612 0.92 80.6 338 0.92

95.5 - 112.0 141 590 0.89 77.8 326 0.89

112.0 - 128.5 137 574 0.87 75.7 317 0.87

128.5 - 145.0 130 545 0.82 71.9 301 0.82

145.0- 161.5 126 527 0.80 69.5 291 0.80

161.5 - 178.0 120 504 0.76 66.4 278 0.76

160

• 140

.• 120

100

• 80

.o 60

0

S40

C 20

. . . . . . . . . .

Energy deposition

.... Fuel enthalpy

0

0 20 40 60 80 100

Axial coordinate (mm)

120 140 160 180

Fig. G-6.4. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6 Code

for Fuel Rod #H6T

G-116
#H6T Iq=i lWirradieateCladditng) undertR Tss

1.2

ti

0

1.0

0.8

0.6

0.4

0.2

1 2 3 4

Radial fuel coordinate (mm)

1.2

03

8'

1.0

0.8

0.6

0.4

0.2

2 3

Radial fuel coordinate (mm)

4

Fig. G-6.5. U235 and Pu 2 39 Radial Distributions of Energy Deposition for Fuel Rod #H6T

G-1 17
fu U16 T [ ~ ~ Indljdu& ~ lRfabi~ncated Fuel Rod

1.2

0

1.0

0.8

0.6

0.4

0.2

Radial fuel coordinate (mm)

120

100

U

U

C.

C

80

60

40

20

0

1.0 1.5 2.0 2.5 3.0 3.5 4.0

Radial fuel coordinate (mm)

Fig. G-6.6. Radial Distributions of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #H6T

G-118
#H6T Cýof Rifhbiicatied Fuel Rodsi

300

250

200

• 150

1005-

0

-00

1600

0..

800

400

0

180

150

4)

120

go

60

OU

30

30

-30 0 1 2 3 4 5 6 7 8 9 10

Time (s)

24

1)

12 0

6 -V

U

"

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. G-6.7. Energy and Temperature Characteristics Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes for Fuel Rod #H6T

G-1 19
#H6T Individual Chara6M-O- 6 of Refabricated Fuel Rods .

(Preirradiated Fu•t. Trrdiated Cladding) Under IGR Tests '

2.50

2.00

2 1.50

E!I-U

0.50

0.00

500

0 1 2 3 4 5 6 .7 8 9 10

Time (s)

G,

0.

0U

L0

1.8

1.6

1.4

1.2

"• 1.0

0.

0 0.8

CI

U 0.6

0.4

0.2

0.0

0.09

0.08

0.07

0.06

0.05

0.04

0.03

0.02

0.01

0.00

0 1 2 3 4 5

Time (s)

6 -7 8 9 10

Fig. G-6.8. Cladding Mechanical Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #H6T

. G-120
#H6T lIlndivhdual Cicteristics of Refabricated Fuel Rods - -

I, (Preiradr~aI. ,•- Preirradiated Cladding) under IGR Tests

3.0 2000

1600

F.

0

0

0

C,)

1200

E

800 "

400

0

0 1 2 3 4 5 6 7- 8 9 10

Time (s)

6.0

5.0

,.,,4.0

0

s._

~3.0

-• 2.0)

1.0

0.0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. G-6.9. Fuel Strain and Fission Gas Release Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #H6T

G-121
Individua cthe-an's of Refabricated Fuel Rods H6T (Preirrdiatd Fue rdiated Cladding) under IGR Tests

Table G-6.9. Some Results of PIE for Fuel Rod #116T

Characteristic Value

I. Measured parameters of cladding oxidation and cladding

deformation

1.1. Cladding thickness at elevation 90 mm for different azimuthal

angles (pim):

00 705

900 677

1800 677

2700 700

1.2. ZrO2 thickness at elevation 90 mm for different azimuthal angles

(Pm):

00 5

900 5

1800 5

2700 5

1.3. ctZr(O) thickness at elevation 90 mm for different azimuthal angles

(jim):

00 0

900 0

1800 0

2700 0

1.4. Clad hoop strain at elevation 90 mm (%) 0

2. Measured parameters for FGR analysis

2.1. Internal gas composition (% by volume):

He 93.85

N2 0.13

02 0.02

Ar 0.004

CO2 0.01

Kr 0.59

Xe 5.4

2.2. Free gas volume (cm3

) 6.88

2.3. Gas pressure inside fuel rod under normal condition (MPa) 1.79

2.4. Kr concentration in fuel (cm3/g fuel) 0.14

3. Measured parameters of cladding hydriding

3.1. Coefficient of hydride orientation (per-unit) 0.25

3.2. Hydrogen concentration (% by weight) 3.4 10-3

G-122
#H6T I I ýndividual charcteristics of Refabricated Fuel Rods ' --

(Preirradal• 0 eJ Preirradiated Cladding) under IGR Tests

.I

Table G-6.10. General Characteristic of Fuel Rod #H6T

Parameter Unit Value

Experiment FRAP-T6 SCANAIR

I Type of coolant - water water water

2 Burnup MWd/kg U 49.3 49.3 49.3

3 Energy deposition in fuel rod callg fuel 141 141 141

4 Peak fuel enthalpy cal/g fuel - 87 83

5 Peak fuel temperature K - 1920 1813

6 Peak clad temperature K - 432 414

7 Fuel rod failure Yes, No No No -

8 Type of failure:

- cladding rupture due to ballooning Yes, No No No

- cladding rupture due to PCMI Yes, No No No

- fragmentation of fuel rod Yes, No No -

9 Failure time s -

10 Fuel enthalpy at failure cal/g fuel - -

I 1 Outer cladding temperature at failure K - -

12 Internal gas pressure at failure MPa -

13 ZrO2 thickness after test') pm 5 5.00

14 Residual clad hoop strain:

- peak value for ballooning area % - - -

- other location1) % 0 0.77 0

15 Kr concentration in internal gas % by volume 0.59 0.65 0.31

composition after test

16 Xe concentration in internal gas % by volume 5.40 3.92 1.86

16 composition after test - .

17 Kr concentration in fuel after test cm3/g fuel 0.14 0.15 0.20

"Calculated values by FRAP-T6 and SCANAIR codes are average along height or fuel rod excluding ballooning region

G-123

G-125
#H7T (Prcirnflg~lfl i uid 4h Cladding) i~hd~ilGR-Tetsts3⁄4i,

Positi =n

PositionW

Fig. G-7.1. Appearance of Fuel Rod #H7T (photographs and X-ray photograph)

G-126
InLlI l I(Il 1ar t, I IQS Ot t< Cabrl[Cete VL I C ROC S

#H7T I Pre;' iatlCldiniý undcr IGR

Position I

Position 2

Position 2

2 'f

Fig. G-7.2. Cross-Section and Cladding Microstructure for Fuel Rod #H7T at 33 mm Elevation

G-127
#H7T

Pn-itinn I

Pnoilioni,

Fig. G-7.3. Cross-Section and Cladding Microstructure for Fuel Rod #H7T at 103 mm Elevation

G-128
#H7T

PositionW-1

PositiontMl

Fig. G-7.4. Cross-Section and Cladding Microstructure for Fuel Rod #H7T at 158 mm Elevation

G-129
#H7T I (Prirrid Ia d Cladding) unider IGR Tests I

Position 2

Fig. G-7.5. Fuel Microstructure for Fuel Rod #H7T at 33 mm Elevation

G-130
#H7T h~~'d~tdiii1 CiEitcsf ~ earicated Fuel Rd .

~~j~ir~a~iad Cladding) wide'r iGRk-Tes

Table G-7.1. Time Dependent Energy Characteristics of Fuel Rod #H7T

Reac- Cumulative number of fissions Power Energy

tor in fuel rod (fiss) of fuel deposition

Time energy rod in fuel rod

(s) deposi- U. U 2 38 

pu

2 39 Pu24 Other Total (kW) ca~ g J/g fuel

ti(n%) xlO-14 xI0-13 xI0"14 XO"14 iso- X10"14 fuel

N topes

I _xl01,

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

9.0

10.0

20.0

30.0

0o

0.000

1.050

5.030

6.580

8.590

11.30

15.30

22.00

34.20

54.80

75.80

86.70

90.50

91.90

92.50

93.00

93.40

93.80

94.10

94.30

94.60

94.80

94.90

95.30

95.60

95.90

96.10

96.50

96.90

98.30

98.90

100.0

0.000

0.068

0.328

0.429

0.560

0.737

0.999

1.430

2.230

3.570

4.940

5.650

5.900

5.990

6.030

6.060

6.090

6.110

6.130

6.150

6.160

6.180

6.190

6.210

6.230

6.250

6.260

6.290

6.310

6.410

6.450

6.520

0.000

0.016

0.078

0.103

0.134

0.177

0.239

0.343

0.534

0.857

1.180

1.350

1.410

1.440

1.450

1.450

1.460

1.460

1.470

1.470

1.480

1.480

1.480

1.490

1.490

1.500

1.500

1.510

1.510

1.540

1.540

1.560

0.000

0.097

0.466

0.610

0.796

1.050

1.420

2.040

3.170

5.080

7.020

8.040

8.390

8.510

8.570

8.620

8.660

8.690

8.720

8.740

8.760

8.780

8.800

8.830

8.860

8.890

8.910

8.940

8.980

9.110

9.160

9.270

0.000

0.039

0.188

0.246

0.321

0.422

0.572

0.820

1.280

2.050

2.830

3.240

3.380

3.430

3.450

3.470

3.490

3.500

3.510

3.520

3.530

3.540

3.540,

3.560

3.570

3.580

3.590

3.600

3.610

3.670

3.690

3.730

0.000

0.080

0.382

0.500

0.653

0.859

1.160

1.670

2.600

4.170

5.760

6.590

6.880

6.980

7.030

7.070

7.100

7.120

7.150

7.170

7.180

7.200

7.210

7.240

7.270

7.290

-7.300

7.330

0.000

0.206

0.989

1.300

1.690

2.230

3.020

4.330

6.730

10.80

14.90

17.10

17.80

18.10

18.20

18.30

18.40

18.50

18.50

18.60

18.60

18.60

18.70

18.80

18.80

18.90

18.90

19.00

19.10

19.40

19.50

0.000

1.180

3.900

4.950

6.490

9.090

14.10

24.70

46.00

66.30

46.40

17.90

5.990

2.570

1.670

1.410

1.210

1.040

0.907

0.798

0.710

0.637

0.577

0.466

0.393

0.341

0.302

0.266

0.221

0.060

0.033

0.000

0.000

2.480

11.90

15.60

20.40

26.80

36.30

52.10

81.10

130.0

180.0

206.0

215.0

218.0

220.0

221.0

222.0

223.0

224.0

225.0

225.0

226.0

226.0

227.0

228.0

229.0

230.0

231.0

232.0

237.0

239.0

244.0

0.000

10.40

49.80

65.30

85.40

112.0

152.0

218.0

339.0

544.0

753.0

862.0

900.0

913.0

921.0

925.0

929.0

933.0

938.0

942.0

942.0

946.0

946.0

950.0

954.0

959.0

963.0

967.0

971.0

992.0

1000.

1021.

*7.360

7.470

7.510

7.600 1 19.70 I

Maximum value of power is 66.3 kW (t - 3.40 s).

1) Current energy deposition per maximum energy deposition (at infinite time)

G-131
#H7T I 1ndivid~f~Ei o ReAbnal~icid Fuil Rds I~~~~_U MPORFt edCddn)udc1Rst:. l"e 

Table G-7.2. Axial Energy Characteristics of Fuel Rod #H7T

Axial Cumulative number of fissions Maxi- Energy deposition

coordi- at axial interval (fiss) mum at infinite time*

nate powerof

from U"S U38 Pu" 9 Pu24' Other Total fuel rod cal/g J/g perlower of xl0 - xl0- xI0.t3 X10.13 iso- xl0"t3 (kW) fuel fuel unitO3 end oftoe -3 s

fuel rod topes t=3.40s

(mm) x104

10.0

15.0

20.0t)

25.0

30.0

35.0

40.0

45.0

50.0

55.0

60.0

65.0

70.0

75.0

80.0

85.0

90.0

95.0

100.0

105.0

110.0

0.000

0.000

0.467

2.340

2.340

2.340

2.340

2.340

2.570

2.440

2.350

2.320

2.280

2.280

2.340

2.340

2.330

2.360

1.150

1.150

2.130

2.170

2.130

2.040

1.920

1.870

1.880

1.910

1.940

1.920

1.900

1.900"

1.420

1.420

0.566

0.000

0.000

0.000

0.918

4.590

4.590

4.590

4.590

4.590

5.930

5.710

5.580

5.600

5.600

5.670

5.900

5.960

6.000

6.150

2.830

2.830

5.000

0.000

0.000

0.623

3.120

3.120

3.120

3.120

3.120

3.580

3.410

3.300

3.260

3.220

3.220

3.310

3.310

3.280

3.310

1.680

1.680

3.140

3.190

3.130

2.990

2.820

2.740

2.750

2.810

2.870-

2.850

2.820

2.830

2.080

2.080

0.833

0.000

0.000

0.000

0.247

1.240

1.240

1.240

1.240

1.240

1.450

1.380

1.320

1.310

1.290

1.290

1.320

1.320

1.320

1.330

0.681

0.681

0.000

0.000

0.439

2.190

2.190

2.190

2.190

2.190

2.630

2.620

2.620

2.620

2.640

2.650

•2.670

2.700

2.740

2.780

1.320

1.320

2.550

2.590

2.620

2.640

2.650

2.660

. 2.660

2.650

2.630

2.610

2.580

2.540

1.620

1.620

0.647

0.000

0.000

0.000

1.350

6.740

6.740

6.740

6.740

6.740

7.660

115.0

120.0

125.0

130.0

135.0

140.0

145.0

150.0

155.0

160.0

165.0

170.0

175.0

180.02).

185.0

5.270

5.340

5.220

5.000

4.920

4.970

5.050

5.120

5.010

4.850

4.730

3.390

3.390

1.360

0.000

1.270

1.290

1.270

1.210

1.150

1.110

1.120

1.140

1.160

1.160

1.140

1.140

0.842

0.842

0.337

0.000

7.290

7.020

6.950'

6.860

6.850

7.030

7.030

6.990

7.070

3.540

3.540

6.600

6.710

6.590

6.290

5.930

5.770

5.800

5.910

6.030

5.980

5.910

5.920

4.380

4.380

1.750

0.000

0.000

0.000

0.453

2.270

2.270

2.270

2.270

2.270

2.580

2.450

2.360

2.340

2.310

2.310

2.370

2.370

2.350

2.380

1.190

1.190

2.220

2.260

2.220

2.120

2.000

1.940

1.950

1.990

2.030

2.010

1.990

1.990

1.470

1.470

0.589

0.000

0.000

0.000

279.0

279.0

279.0

279.0

279.0

279.0

251.0

248.0

246.0

244.0

242.0

242.0

241.0

242.0

243.0

244.0

243.0

243.0

239.0

238.0

237.0

235.0

234.0

233.0

232.0

'231.0

230.0

230.0

229.0

228.0

227.0

227.0

227.0

0.000

0.000

0.000

1168.

1168.

1168.

1168.

1168.

1168.

1051.

1038.

1030.

1021.

1013.

1013.

1009.

1013.

1017.

1021.

1017.

1017.

1000.

996.0

992.0

984.0

980.0

975.0

971.0

967.0

963.0

963.0

959.0

954.0

950.0

950.0

950.0

0.000

0.00

0.00

1.00

1.00

1.00

1.00

1.00

1.00

0.90

0.89

0.88

0.87

0.87

0.87

0.86

0.87

0.87

0.87

0.87

0.87

0.86

0.85

0.85

0.84

0.84

0.84

0.83

0.83

0.82

0.82

0.82

0.82

0.81

0.81

0.81

0.00

All numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate ± 2.5 nun

1) Initial coordinate of fuel is 21.5 mm.

2) End coordinate of fuel is 179.5 nun.

3) Current value per maximum value.

G-132
#H7T j~~j~rradiated Cl~1dhig) tinder ICIR Tests

Table G-7.3. Radial Energy Characteristics of Fuel Rod #H7T

Coordinates of fuel zones (mm)

Characteristics* I zone 2 zone 3 zone 4 zone

1.2 -2.811 2.811-3.432 3.432-3.704 3.704-3.790

Number of fissions x 10-14 (fiss) 2.400 1.410 0.692 0.225

Power of fuel rod') (kW) 7.950' 4.670 2.290 0.746

U2

35 Energy deposition2 ) (callg fuel) 78.10 76.50 75.00 73.30

Energy deposition2) (J/g fuel) 327.0 320.0 314.0 307.0

Energy deposition 3

) (per-unit) 1.000 0.980 0.960 0.939

Number of fissions x 10"t2 (fiss) 6.240 3.510 1.620 0.488

Power of fuel rod') (kW) 0.204 0.115 0.053 0.016

U238 Energy deposition2 ) (callg fuel) 2.000 1.880 1.730 1.570

Energy deposition2 ) (J/g fuel) 8.370 7.870 7.240 6.570

1 Energy deposition3

) (per-unit) 1.000 0.940 0.865 0.785

Number of fissions x 10"4 (fiss) 2.830 1.920 1.320 0.750

Power of fuel rod') (kW) 9.640 6.560 4.500 2.560

Pu2 39 Energy deposition2 ) (cal/g fuel) 95.00 108.0 148.0 252.0

Energy deposition2) (J/g fuel) 398.0 452.0 620.0 1055.

Energy deposition 3

) (per-unit) 0.377 0.429 0.587 1.000

Number of fissions xl0"-3 (fiss) 10.90 7.730 5.560 3.320

Power of fuel rod) (kW) 3.650 2.600 1.870 1.120

Pu241 Energy deposition2

) (Cal/g fuel) 36.00 42.60 61.30 110.0

Energy deposition2) (J/g fuel) 151.0 178.0 257.0 460.0

Energy deposition3

) (per-unit) 0.327 0.387 0.557 1.000

Number of fissions x 10-" (fiss) 2.700 1.670 0.970 0.462

Other Power of fuel rod') (kW) 0.009 0.006 0.003 0.002

isoto- Energy deposition2

) (cal/g fuel) 0.090 0.093 0.108 0.154

pes Energy deposition') (J/g fuel) 0.380 0.390 0.450 0.640

I Energy deposition3

) (per-unit) 0.585 0.601 0.701 1.000

Number of fissions x10-t4 (fiss) 6.380 4.140 2.590 1.310

Power of fuel rod') (kW) 21.40 13.90 8.700 4.420

Total Energy deposition2) (cal/g fuel) 211.0 229.0 286.0 436.0

Energy deposition2 ) (J/g fuel) 883.0 959.0 1197. 1825.

Energy deposition3 1 (per-unit) 0.484 0.525 0.656 1.000

at time of 3.40 s, 2) at infinite time, 3) Current value per maximum value.

All numerical values of characteristics were calculated for undamaged part of fuel stack only (See Table C.2.2.)

G-133
SFuel... .. . I

#H7T CuClalted yF -C ould #HTT

Table G-7.4. Fuel Enthalpy Vs. Time Calculated by FRAP-T6 Code for Fuel Rod #117T

Time Enthalpy at fuel radius Fuel e Energy deposition

Time _ (cal[2! fuel) _Fuel entalp _ _ in fuel rod

(S) 1.20 mnm 2.82 mm 3.47 mm 3.79 mm cal/g fuel I J/g fuel cal/g fuel J/g fuel

0.0

1.0

2.0

2.2

2A

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5A

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

2.59

11.6

15.3

20.0

26.3

35.6

51.3

80.7

133

189

220

229

230

229

225

222

217

213

207

202

196

.189

172

156

141

129

93.6

0.00

2.58

11.3

14.7

18.9

24.5

32.6

46.5

72.7

120

168

189

190

186

180

174

167

161

154

146

139

133

128

117

109

102

96.1

77.0

11.4

0.00 0.00

2A9

10.6

13.5

16.7

20.8

26.3

35A

50.8

82.3

119

133

140

134

128

124

117

108

101

95.3

91.8

89.3

87.4

83.8

80.8

78.0

75.2

64.9

11.0

2.35

9.78

11.9

14.2

16.6

19.0

21.0

25.5

40.5

76.0

99.5

109

102

99.3

96.2

86.8

77.9

72.0

70.1

69.4

69.0

68.8

68.2

67.5

66.3

64.9

58.4

0.00

2.55

11.2

14.5

18.5

23.8

31.4

44.0

67.5

111

158

181

187

184

179

174

168

162

156

150

144

139

134

124

115

107

99.6

78.3

11.4

0.00

10.7

46.8

60.5

77.4

99.5

131

184

283

463

662

758

782

769

750

730

706

678

- 652

627

604

583

563

519

481

447

417

328

47.9

0.00

2.47

11.9

15.6

20.3

26.8

363

52.0

80.8

130

179

206

215

218

220

221

222

223

224

225

225

226

226

228

228

229

230

232

0.00

10.4

49.8

65.3

852

112

152

218

339

543

751

862

900

914

921

927

932

935

939

942

944

947

949

954

957

961

963

973

11.8 10.8 239 1004

Radial enthalpy distribution and fuel enthalpy are presented at elevation 29.4 mm

MIximum value of fuel entlhalpy is 186.7 calg fuel (t=3.98 s)

) All numerical values are presented at elevation vith peak power

G-134
#H7T of Reiabic'dF Rdi

ditdCladding) unfder lGktesisi>i

Table G-7.5. Energy Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel

Rod #H7T

Time Energy Linear Fuel Energy of LClad-to-coolant heat

(s) (ea/g fuel) (kW/r) (cag fuel) reaction'l) (cag fuel) (kW/m2K)

FRAP-T6 I SC Ai FRAP-T6 eFRAP-T6 ISCAAIR F1AP-T6 SCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

2.83

13.6

17.8

232

30.6

41A

59A

92.2

148

205

235

245

249

251

253

254

255

256

257

257

258

259

260

261

262

263

265

274

0.00

10.1

332

42.2

55.3

77A

120

210

392

565

399

154

51.6

22.1

14.3

12.1

10.3

8.89

7.85

6.90

6.14

5.49

4.97

4.02.

3.37

2.92

2.59

1.89

023

0.00

2.55

11.2

14.5

18.5

23.8

31.4

44.0

67.5

111

158

181

187

184

179

174

168

162

156

150

144

139

134

124

115

107

99.6

78.3

11.4

0.00

2.50

11.9

15.1

19.7

25.9

33.7

48.8

77.5

116

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.02

0.04

0.06

0.06

0.06

0.06

0.06

0.06

0.06

0.06

0.06

0.06

0.06

0.06

0.06

0.06

0.06

0.00

0.00

026

1.03

2.30

4.24

7.30

12.3

21.9

33.3

36.7

42.8

49.6

56.4

63.4

74.1

88.2

101

110

117

123

129

133

144

153

161

168

191

266

0.00

0.01

0.08

0.47

1.39

2.78

4.51

7.64

13.4

23.5

0.00

0.03

1.73

3.11

4.63

6.74

10.3

172

26A

5.29

1.93

2.27

2.21

2.25

2.68

5.46

9.31

142

17.7

15.1

13.6

12.6

11.7

10.0

8.87

8.01

7.30

522

0.46

0.00

0.10

0.31

228

3.51

5.07

7.06

11.2

20.5

27.5

I I A. A. A. a a

1) All nunerical values ae presented at elevation with peak povcr

G-135
#H7T I:didtI Cscfbiae Fel Rd

[(Pieiýiý Iditd Ctaddinlg) iirdii, lGRies

Table G-7.6. Temperature Variation, Fission Gas Release and ZrO2 Thickness Vs. Time for Fuel

Rod #H7T Calculated by FRAP-T6 and SCANAIR Codes

Fuel centerline Fuel surface Clad outer Average

Time Felpsrace e radurute Fission gas release ZrO22)

(smp eraturel) t emperature) (%) thickness

(K) (K) (K) (4n

FRAP-T6 I SCANAIR FRAP-T6 I SCANAIR FRAP-T6 SCANAIR FRAP-T6 SCANAIR FRAP-T6

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

338

480

534

601

691

820

1031

1414

2037

2572

2804

2868

2876

2863

2843

2817

2786

2755

2716

2674

2626

2574

2431

2279

2131

1994

1576

483

293

333

479

527

596

689

802

1013

1399

1920

293

334

452

484

518

553

588

616

680

887

1354

1650

1764

1683

1647

1608

1491

1378

1302

1278

1269

1263

1260

1254

1244

1229

1210

1125

467

293

332

466

506

560

628

709

854

1072

1144

293

315

389

395

399

405

412

423

434

629

1060

1230

1201

1221

1200

1025

748

533

423

420

418

416

414

411

409

408

406

401

381

293

305

376

383

385

388

391

397

406

445

0.00

0.07

0.24

0.32

0.43

0.59

0.85

1.34

2.49

4.63

7.56

10.8

17.1

18.7

18.7

18.8

18.8

18.8

18.8

18.8

18.8

18.8

18.8

18.8

18.8

18.8

18.9

18.9

18.9

0.00

0.25

0.90

1.05

1.27

1.69

2.04

2.50

2.97

3.71

.5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.03

5.06

5.10

5.13

5.15

5.15

5.15

5.15

5.15

5.15

5.15

5.15

5.15

5.15

5.15

5.15

5.15

5.15

1) All numerical values are presented at elevation with peak power

2) Initial ZrO2 thickness is 5 pim

G-136
#H7T Individua ctedstics of Refabricated Fuel Rods

I(Preiriadladi , Preirradiated Cladding) under IGR Tests,-.

Table G-7.7. Mechanical Characteristics of Fuel Rod #H7T Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes

Clad outer Fuelhoop Fuel - clad gap Clad hoop Clad hoop Internal gas Time temperature1) strain1 

(s) (K) (%) width" (mm) strain' (%) stress" (MPa) pressure (MPa)

FRAP-T61SCAN FRAP-T6 SCANAIRFRAP-T6[SCANAIR FRAP-T61SCANAIR FRAP-T6 SCANA FRAP-T61SCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

315

389

395

399

405

412

423

434

629

1060

1230

1201

1221

1200

1025

748

533

423

420

418

416

414

411

409

408

406

401

381

293

305

376

383

385

388

391

397

406

445

0.00

0.06

0.31

0.40

0.51

0.66

0.87

1.22

1.87

3.01

4.40

5.08

5.87

6.11

6.02

5.89

5.67

5.42

5.20

4.96

4.75

4.54

4.33

3.85

3.44

3.08

2.77

1.64

0.08

0.00

0.03

0.14

0.17

0.23

0.30

0.39

0.59

1.02

1.84

0.04

0.04

0.03

0.02

0.02

0.02

0.01

0.00

0.00

0.00

0.00

0.07

0.30

0.29

0.30

0.30

0.31

0.32

0.33

0.34

0.35

0.35

0.36

0.38

0.40

0.41

0.42

0.46

0.52

0.07

0.07

0.07

0.07

0.06

0.06

0.06

0.05

0.04

0.01

0.01

0.02

0.08

0.08

0.09

0.09

0.11

0.23

0.75

1.70

2.88

5.35

12.2

12.2

12.2

12.5

12.3

12.1

12.1

12.1

12.1

12.0

12.0

12.0

12.0

12.0

12.0

12.0

12.0

0.01

0.02

0.07

0.08

0.09

0.09

0.10

0.11

0.14

0.21

8.81

8.98

9.43

9.56

9.70

9.85

10.0

136

455

358

63.3

13.4

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

8.59

8.80

9.37

9.58

9.82

10.1

10.5

11.0

12.1

13.9

1.70 1 1.70

1.75

1.83

1.85

1.87

1.90

1.94

1.99

2.05

2.14

2.23

2.32

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

1.74

1.83

1.85

1.88

1.91

1.94

1.99

2.04

2.09

_________ _________ 1. _________ ~. _________ i.& __________ .

I) All numerical valucs are presented at elevation Aith peak powcr

G-137
#H7T Individual Characteriids of Refabricated Fuel Rods

(Preihradiaied FueIMr1tradiated Cladding) under IGR Tests:

Table G-7.8. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #H7T

Axial interval Energy deposition at infinite time Fuel enthalpy

from-to e nat time (t=3.98 s)

(mm)-(mm) caVg fuel Jig fuel per-unit cal/g fuel J/g fuel per-unit

21.5-37.3 279 1169 1.00 187 782 1.00

37.3-53.1 269 1127 0.96 180 754 0.96

53.1 - 68.9 246 1029 0.88 164 689 0.88

68.9- 84.7 242 1013 0.87 162 678 0.87

84.7- 100.5 243 1019 0.87 .163 682 0.87

100.5 - 116.3 241 1008 0.86 161 675 0.86

116.3 - 132.1 236 987 0.84 158 661 0.84

132.1 - 147.9 232 972 0.83 155 651 0.83

147.9 - 163.7 230 962 0.82 154 644 0.82

163.7- 179.5 227 952 0.81 152 637 0.81

300

U

250

. 200

• 150

• 100 0

0.

b50

4 Energy deposition

e-.Fuel enthalpy

0

20 40 60 80 100 12

Axial coordinate (mm)

0 140 160 180

Fig. G-7.6. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6 Code

for Fuel Rod #117T

G-138
#H7T ,Inddividual.acteristics of Refai'icated Fuel Rods l.(Prirradi~at iel, Preirradiated Cladding) under IGR Tests

1.2 -r

U235

-4-

1.0

0.8

0.6

0.4

I.

'I

II m F'

i i iL i

0.2 ! I 3

I 2 3 4

Radial fuel coordinate (mm)

1.2

03

0

In

00

1.0

0.8

0.6

0.4 -1

I vI

0.2 -I- I

1 2 3 4

Radial fuel coordinate (mm)

Fig. G-7.7. U235 and Pu 239 Radial Distributions of Energy Deposition for Fuel Rod #H7T

G-139
#H7T I Individuai Charactdis•icsofRefabricated Fuel Ros .,'

:(Preiniiadiated Fuel.qi'"rdiated Cladding) under IGR Tests -

1.2

r

014V

0

1.0

0.8

0.6

0A

0.2

I 2 3 4

Radial fuel coordinate (mm)

250

200

a- 150

.~100

50

0

1.0 1.5 2.0 2.5 3.0 3.5 4.0

Radial fuel coordinate (mm)

Fig. G-7.8. Radial Distributions of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #H7T

G-140.
#H7T hndividaClicteristics of Refabricated Fuel Rods I (Preirradi •-Eg1,Preirradiated ClAdding) under Ig Tests

600 300

500 +

I 1 -

-- FRAP-T6

.... SCANAIR

SPower of fuel rod

- Energy deposition

-- CF- Fuel enthalpy

0 Leakage ofenergy

Clad oxidation enerav

4 .4. 4 1-

400

0

-; 300

0

• 200

100

0

T T T T

I/1

LLK/

250

U

200

(0

150• U

100

5O

0

0 1 2 3 4 5 6 7 8

10

9 10

Time (s)

3000

2500

2000

1500

E

1000

500

36

30 -•

30 U

24

18 E

12

6 U

0

0 1 2 3 4 5

Time (s)

6 7 8 9 10

Fig. G-7.9. Energy and Temperature Characteristics Vs. Time Calculated by FRAP-I6 and

SCANAIR Codes for Fuel Rod #H7T

G-141
#H7T lfidiv'idual'Chactenecs 6f Refabricated Fuel Rods

(Preirradiated FUe•!•,; adiated Cladding) under IGR Tests

2.5

2.0

1.5

1.0

E

4.)

0.5

0.0

500

400

300

0.

200

100

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

15

12

U. 0

0

9

6

____ _ __ _ -• FRAP-T6

.... SCANAIR

......... 73 -0- Clad hoop strain

- -.---" Fuel-clad gap viidth

0.5

0.4

SE

0.3 -5

0.2

0.1

0.0

3

0

0 1 2 3 4 5 6 7 10

Time (s)

Fig. G-7.10. Cladding Mechanical Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod NH7T

G-142
#1-17T

I IndivjduChi csies •f .car~ ueRods: - :

.... reirradiated Cladding) under ,GR Tests

10.0

8.0.

-3000

2400

0

0

0x6.0

4.0.

18oo 2

E

1200

._

U2o

U,

2.0

0.0 q

600

5 6 7 8 9 10

Time (s)

20

iqC

5 6 8 9 10

Time (s)

Fig. G-7.11. Fuel Strain and Fission Gas Release Vs. Time Calculated by FRAP-T6 and SCANAiR

Codes for Fuel Rod #H7T

G-143
4ndividual Chir sgfRefabricated 00•-n Fuel Rods # 7 T (Preirridiatid Fue&tr diated Cladding) under IGR TestsTable G-7.9. Some Results of PIE for Fuel Rod N1U7T

Characteristic Value

I. Measured parameters of cladding oxidation and cladding

deformation

1.1. Cladding thickness at elevation 33, 103, 158 mm correspondent to

different azimuthal angles (pan):

00 663 691 -

900 R 677 680

1800 710 677 -

2700 677 663 -

1.2. ZrO2 thickness at elevation 33, 103, 158 mm correspondent to

different azimuthal angles (pm):

00 5 5 5

900 5 5 5

1800 5 5 5

2700 5 5 5

1.3. aZr(O) thickness at elevation 33, 103, 158 mm correspondent to

different azimuthal angles (pm):

00 0 0 0

900 0 0 0

1800 0 0 0

2700 0 0 0

1.4. Clad hoop strain at elevation 33, 103, 158 mm, respectively(%) 10.1 3.4 22.8

2. Measured parameters for FGR analysis

Internal gas composition (% by volume):

He

N2

02

Ar

CO2

Kr

Xe

2.2. Free gas volume (cm3)

2.3. Gas pressure inside fuel rod under normal condition (MPa)

2.4. Kr concentration in fuel (cm 3

1k fuel)

3. Measured parameters of cladding hydriding

3.1. Coefficient oflhydride orientation (per-unit) 0.19

3.2. Hydrogen concentration (% by weight) -

G-144
#H7T I lndividual Cli-acteristics of Refabricated Fu.el Rods -

(Preirradiýa 4ej Preirradiated Cladding)'under IGR Tests

Table G-7.10. General Characteristic of Fuel Rod #H7T

Parameter Unit Value

Experiment FRAP-T6 SCANAIR

! Type of coolant water water water

2 Burmup MWd/kg U 47.3 47.3 47.3

3 Energy deposition in fuel rod cal/g fuel 244 244 244

4 Peak fuel enthalpy cal/g fuel - 187 -

5 Peak fuel temperature K - 2876 -

6 Peak clad temperature K - 1231 -

7 Fuel rod failure Yes, No Yes Yes -

8 Type of failure:

- cladding rupture due to ballooning Yes, No Yes Yes -

- cladding rupture due to PCMI Yes, No No No

- fragmentation of fuel rod Yes, No No -

9 Failure time s - 3.81

10 Fuel enthalpy at failure cal/g fuel - 182

11 Outer cladding temperature at failure K - 1229

12 Internal gas pressure at failure MPa - 2.33

13 ZrO2 thickness after test Pm 5 5.15-

14 Residual clad hoop strain:

- peak value for ballooning area % 10.1 11.95

- other location1) % 3.4 2.16

15 Kr concentration in internal gas % by volume - 2.84

composition after test

16 Xe concentration in internal gas % by volume 17.02

16 composition after test I__yvolume 17 .0

17 Kr concentration in fuel after test cm3/g fuel - 0.15

')Calculated values by FRAP-T6 and SCANAIR codes are average along height of fuel rod excluding ballooning region

G-145

r

G-147
#H8T MWMG "Oear-ie FuelRos I ~(rcidi 1'P~niditedCladdirg) tender 16R Tet

PositionT

_ 

Axial coordinate 

(mm)

IAxial coordinate (am)

Fig. G-8.1. Appearance of Fuel Rod #H8T (photographs and X-ray photograph) and Profilometry

G-148
#H8T

Position 1

Fig. G-8.2. Cross-Section and Cladding Microstructure for Fuel Rod #H8T at 90 mm Elevation

G-149
#H8T

Position 1

Fig. G-8.3. Fuel Microstructure for Fuel Rod #H8T at 90 mm Elevation

G-150
#H8T -f Rrabted ding F't-d'* RIls Test 

I ~crrazatc~1,'j~iradated Cladding) unhdeIGTst

Table G-8.1. Time Dependent Energy Characteristics of Fuel Rod #H8T

Reac- Cumulative number of fissions Power Energy

tor in fuel rod (fiss) of fuel deposition

Time energy rod in fuel rod

(s) deposi- U Pu239 Pu24 1 Other Total (kW) cag Jg fuel

tin) x10-" xlO13 xl0-14 XI0"14 iso- xl0"-4 fuel

topes

X l 10 11

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

.5.6

5.8

6.0

6.5

7.0

7.5

8.0

9.0

10.0

20.0

30.0

o0

0.000

0.575

2.300

2.790

3.330

3.920

4.590

5.350

6.250

7.370

8.870

11.10

14.80

21.40

33.00

49.10

64.50

76.00

83.10

87.20

89.50

91.00

92.00

93.60

94.70

95.40

95.90

96.60

97.10

98.70

99.10

100.0

0.000-

0.017

0.068

0.082

0.098

0.115

0.135

0.158

0.184

0.217

0.261

0.327

0.436

0.631

0.971

1.440

1.900

2.240

2.450

2.570

2.640

2.680

2.710

2.750

2.790

2.810

2.820

2.840

2.860

2.900

2.920

2.940

0.000

0.004

0.014

0.017

0.021

0.024

0.028

0.033

0.039

0.045

0.055

0.069

0.091

0.132

0.204

0.303

0.398

0.469

0.513

0.538

0.553

0.562

0.568

0.578

0.585

0.589

0.592

0.596

0.599

0.609

0.612

0.617

0.000

0.023

0.093

0.113

0.135

0.159

0.186

0.217

0.253

0.299

0.360

0.450

0.600

0.869

1.340

1.990

2.610

3.080

3.370

3.530

3.630

3.690

3.730

3.790

3.840

3.870

3.890

3.920

3.940

4.000

4.020

4.050,

0.000

0.009

0.037

0.045

0.054

0.064

0.074

0.087

0.101

0.120

0.144

0.180

0.240

0.348

0.536

0.796

1.050

1.230

1.350

1.420

1.450

1.480

1.490

1.520

1.540

1.550

1.560

1.570

1.580

1.600

1.610

1.620

0.000

0.017

0.069

0.084

0.100

0.118

0.138

0.161

0.188

0.221

0.267

0.334

0.445

0.644

0.992

1.470

1.940

2.280

2.500

2.620

2.690

2.740

2.770

2.810

2.850

2.870

2.880

2.900

2.920

2.970

,2.980

3.010

0.000

0.050

0.200

0.242

0.289

0.341

0.399

0.465

0.543

0.640

0.770

0.964

1.290

1.860

2.870

4.260

5.600

6.600

7.220

7.570

7.780

7.900

7.990

8.130

8.220

8.280

8.330

8.390

8.430

8.570

8.610

8.690

0.000

0.286

0.574

0.639

0.708

0.786

0.884

1.020

1.230

1.590

2.230

3.480

6.020

10.90

17.90

20.70

17.10

11.40

6.720

3.850

2.330

1.530

1.110

0.680

0.480

0.328

0.238

0.182

0.125

0.026

0.013

0.000

0.000

0.608

2.440

2.950

3.530

4.160

4.870

5.670

6.630

7.810

9.400

11.80

15.70

22.70

35.00

52.00

68.30

80.50

88.10

92.50

95.00

96.60

97.70

99.50

101.0

102.0

102.0

103.0

104.0

106.0

107.0

109.0

0.000

2.550

10.20

12.30

14.80

17.40

20.40

23.70

27.80

32.70

39.30

49.40

65.70

95.00

147.0

218.0

286.0

337.0

369.0

387.0

398.0

404.0

409.0

417.0

423.0

427.0

427.0

431.0

435.0

444.0

448.0

456.0

Maximum value of power is 20.8 kW (t = 4.55 s).

1) Current energy deposition per maximum energy deposition (at infinite time)

G-151
#H8T I•Indivf~dei~' Ci i~lfabriCtcdi Fuel Rods.GR'-T•

Table G-8.2. Axial Energy Characteristics of Fuel Rod #H8T

Axial Cumulative number of fissions Maxi- Energy deposition

coordi- at axial interval (fiss) mum at infinite time*

nate _ power of

from U235 U23

. Pu239 Pu24 t Other Total fuel rod callg J/g perlower xiO-13 x10.11 x10.13 xI0.t 3 iso- xl0"t3 (kW) fuel fuel unit3

)

fuel rod topes t=-4.55s

(mm) xl0"__

10.01)

15.0

20.0

25.0

30.0

35.0

40.0

45.0

50.0

55.0

60.0

65.0

70.0

75.0

80.0

85.0

90.0

95.0

100.0

105.0

110.0

115.0

120.0

125.0

130.0

135.0

-140.0

145.0

150.0

155.0

160.0

165.0

170.0

175.02)

180.0

185.0

0.752

0.752

0.752

0.752

0.755

0.755

0.755

0.755

0.755

0.755

0.713

0.713

0.713

0.713

0.713

0.713

0.713

0.713

1.060

1.070

1.060

1.060

1.050

1.050

1.060

1.070

1.070

1.080

1.080

1.080

1.060

1.020

1.010

1.010

0.000

0.000

1.400

1.400

1.400

1.400

1.500

1.500

1.500

1.500

1.500

1.500

1.620

1.620

1.620

1.620

1.620

1.620

1.620

1.620

2.160

2.220

2.240

2.260

2.260

2.270

2.290

2.310

2.330

2.340

2.320

2.290

2.220

2.110

2.040

2.040

0.000

0.000

1.080

1.080

1.080

1.080

1.080

1.080

1.080

1.080

1.080

1.080

1.020

1.020

1.020

1.020-

1.020

1.020

1.020

1.020

1.410

1.420

1.410

1.410

1.400

1.400

1.400

1.420

1.430

1.440

1.440

1.440

1.410

1.370

1.360

1.360

0.000

0.000

0.440

0.440

0.440

0.440

0.440

0.440

0.440

0.440

0.440

0A40

0.415

0.415

0.415

0.415

0.415

0.415

0.415

0.415

0.556

0.561

0.558

0.555

0.552

0.550

0.554

.0.557

0.563

0.567

0.567

0.565

0.555

0.538

0.532

0.532

0.000

0.000

0.741

0.741

0.741

0.741

0.758

0.758

0.758

0.758

0.758

0.758

0.777

0.777

0.777

0.777

0.777

0.777

0.777

0.777

1.090

1.090

1.100

1.100

1.100

1.100

1.100

1.090

1.080

1.070

1.060

1.040

1.020

1.000

0.978

0.978

0.000

0.000

2.290

2.290

2.290

2.290

2.290

2.290

2.290

2.290

2.290

2.290

2.170

2.170

2.170

2.170

2.170

2.170

2.170

2.170

3.050

3.080

3.060

3.050

3.030

3.020

3.040

3.060

3.090

3.120

3.120

3.100

3.050

2.950

2.920

2.920

0.000

0.000

0.549

0.549

0.549

0.549

0.548

0.548

0.548

0.548

0.548

0.548

0.519

0.519

0.519

0.519

0.519

0.519

0.519

0.519

0.731

0.737

0.733

0.731

0.726

0.725

0.728

0.734

0.741

0.748

0.747

.0.744

0.731

.0.707

0.700

0.700

0.000

0.000

117.0

117.0

117.0

117.0

116.0

116.0

116.0

116.0

116.0

116.0

110.0

110.0

110.0

110.0

110.0

110.0

110.0

110.0

109.0

109.0

108.0

.108.0

108.0

107.0

107.0

106.0

105.0

104.0

103.0

102.0

.101.0

100.0

99.20

99.20

0.000

0.000

490.0

490.0

490.0

490.0

486.0

486.0

486.0

486.0

486.0

486.0

460.0

460.0

460.0

460.0

460.0

460.0

460.0

460.0

456.0

456.0

452.0

452.0

452.0

448.0

448.0

444.0

440.0

435.0

431.0

427.0

423.0

419.0

415.0

415.0

0.000

0.000

1.00

1.00

1.00

1.00

0.99

0.99

0.99

0.99

0.99

0.99

0.94

0.94

0.94

0.94

0.94

0.94

0.94

0.94

0.93

0.93

0.92

0.92

0.92

0.91

0.91

0.91

0.90

0.89

0.88

0.87

0.86

0.85

0.85

0.85

0.00

0.00

All numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate * 2.5 mm.

1) Initial coordinate of fuel is 10.5 mm.

2) End coordinate of fuel is 177.5 mm.

3) Current value per maximum value.

G-152
#H8T I •• tetrrticsdof fuel R7ricated IGRo.Tde <s' 

I ~I ~ kadiatedCladding) under IGR Tests

Table G-8.3. Radial Energy Characteristics of Fuel Rod #H8T

Coordinates of fuel zones (mm)

Characteristics* 1 zone 2 zone 3 zone 4 zone

1.2-2.811 2.811-3.432 3.432-3.704 3.704-3.790

Number of fissions x 10"t4 (fiss) 0.806 0.474 0.233 0.076

Power of fuel rod') (kW) 1.900 1.120 0.549 0.179

U23S Energy deposition2

) (cal/g fuel) 36.40 35.70 35.10 34.30

Energy deposition2

O (J/g fuel) 152.0 149.0 147.0 144.0

Energy deposition3) (per-unit) 1.000 0.981 0.964 0.942

Number of fissions x 10"'2 (fiss) 1.770 0.996 0.459 0.139

Power of fuel rod') (kW) 0.041 0.023 0.011 0.003

U238 Energy deposition2) (callg fuel) 0.789 0.740 0.681 0.618

Energy deposition 2

) (J/g fuel) 3.300 3.100 2.850 2.590

Energy deposition3

) (per-unit) 1.000 0.938 0.863 0.783

Number of fissiohs x 10"14 (fiss) 0.876 0.597 0.411 0.234

Power of fuel rod') (kW) 2.130 1.450 0.999 0.569

Pu239 Energy deposition2) (cal/g fuel) 40.90 46.40 63.90 109.0

Energy deposition2 ) (J/g fuel) 171.0 194.0 267.0 456.0

Energy deposition3) (per-unit) 0.375 0.426 0.586 1.000

Number of fissions x10"13 (fiss) 3.290 2.340 1.690 1.010

Power of fuel rod') (kW) 0.785 0.559 0.403 0.242

Pu24 1 Energy deposition2

) (cal/g fuel) 15.10 17.90 25.80 46.50

Energy deposition2) (Jig fuel) 63.20 74.90 108.0 195.0

Energy deposition3) (per-unit) 0.325 0.385 0.555 1.000

Number of fissions x 10-" (fiss) 0.747 0.460 0.268 0.128

Other Power of fuel rod') (kW) 0.002 0.001 0.001 0.000

isoto- Energy deposition2

) (cal/g fuel) 0.034 0.036 0.041 0.059

pes Energy deposition2

) (J/g fuel) 0.140 0.150 0.170 0.250

Energy deposition3) (per-unit) 0.584 0.601 0.699 1.000

Number of fissions xI0"14 (fiss) 2.030 1.310 0.817 0.413

Power of fuel rod') (kW) 4.860 3.150 1.960 0.992

Total Energy deposition2) (cal/g fuel) 93.10 101.0 125.0 190.0

Energy deposition2 ) (J/g fuel) 390.0 423.0 523.0 795.0

1 Energy deposition 3

) (per-unit) 0.490 0.532 0.658 1.000

i) at time of4.55 s, 2) at infinite time, 3) Current value per maximum value.

All numerical values of characteristics were calculated for undamaged part of fuel stack only (See Table C.2.2.)

G-153
I dni~rdi ••'•r F•uel R•d ;:•.,L

#H8T a bCe

Table G-8.4. Fuel Enthalpy Vs. Time Calculated by FRANPT6 Code for Fuel Rod #118T

Enthalpy at fuel radius 1 Energy deposition T"ime (cat/& fuel) Fuel enthl~py .) E ryin fuelde it~rod

(S) 1.20=7 2.82= I 3.47_ I 3.79 mm iIcal/g fuel J/g fuel l fuel /g [ 

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

32

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

0.59

2.28

2.75

3.26

3.82

4.45

5.17

6.02

7.14

8.72

11.3

14.6

22.8

33.8

49.0

66.2

76.6

83.9

86.3

85.6

83.7

79.7

67.2

57.0

48.0

40.2

21.5

5.16

0.00

0.58

2.18

2.63

3.12

3.66

4.27

4.96

5.78

6.86

8.40

10.9

14.0

21.7

32.1

46.0

58.9

63.8

64.0

60.6

55.0

51.4

46.9

40.7

36.3

31.9

28.0

17.3

5.12

0.00

0.54

2.06

2.48

2.95

3.47

4.05

4.70

5.49

6.52

7.97

102

12.8

19.3

27.5

36.4

38.8

38.7

35.9

32.7

28.9

27.0

25.3

25.9

23.9

22.1

20.3

14.2

5.09

0.00

0.51

1.96

2.36

2.81

3.31

3.86

4.49

525

621

7.54

9.38

11.5

16.2

21.8

22.8

21.3

20.9

19.6

18.1

16.6

16.0

16.0

19.2

18.1

17.4

16.6

12.5

5.06

0.00

0.57

2.17

2.62

3.11

3.65

425

4.94

5.76

6.83

8.36

10.8

13.8

21.2

31.0

43.4

54A

59.7

61A

60.0

56.5

54.0

50.5

44.2

38.8

33.8

29.4

17.6

5.12

0.00

2.39

9.11

11.0

13.0

15.3

17.8

20.7

24.2

28.6

35.0

45.1

57.7

88.7

130

182

228

250

257

252

237

226

211

185

162

142

123

73.8

21.5

0.00

0.59

2.39

2.90

3.47

4.10

4.80

5.60

0.00

2.45

10.0

12.2

14.5

17.2

20.1

23.5

6.55

7.76

9.47

12.2

15.6

24.0

35.3

50.8

68.4

79.4

88.0

92.4

95.5

96.7

97.9

99.8

101

102

102

104

107

27.4

32.5

39.7

51.0

65.3

101

148

213

287

332

369

387

400

405

410

418

423

426

429

436

448

Radial enthalpy distribution and fuel enthalpy are presented at elevation 18.9 mm

Maximun value of fuel enthalpy is 61.4 calfg fuel (t=-5.16 s)

1) All numerical values are presented at elevation With peak poyer

G-154
#H8T eimiiali Cladding) unader IGR~Tes .ts -ý]

Table G-8.5. Energy Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel

Rod #H8T

Energy Linear Energy of Clad-to-coolant heat S) eposition 'w ) Fuel enthalpy') metal-water Leakage of energy transfer coefficient1)

(s) (cal/g fuel) (kW/m) (cal/g fuel) reaction r (cal/g fuel) (kW/m2K) (cal/k fIel)

FRAP-T6 IS5__I_ _ FRAP-T6 FRAP-T6 _AI R FRAP-T6 SCANAIRP

0.0

1.0

2.0

22

2A

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

0.63

2.56

3.11

3.72

4.39

5.14

5.99

7.01

8.31

10.1

13.0

16.7

25.7

37.8

54.4

73.3

85.0

94.2

99.0

102

104

105

107

108

109

110

III

115

0.00

2.29

4.63

5.16

5.72

6.34

7.12

8.19

9.86

12.8

18.4

30.3

48.3

96.0

147

169

139

992

56.1

32.5

17.7

12.9

9.04

5.45

3.95

2.73

1.97

1.02

0.10

0.00

0.57

2.17

2.62

3.11

3.65

4.25

4.94

5.76

6.83

8.36

10.8

13.8

21.2

31.0

43.4

54.4

59.7

61.4

60.0

56.5

54.0

50.5

44.2

38.8

33.8

29.4

17.6

5.12

0.00

0.55

2.13

2.52

3.01

3.56

4.09

4.78

5.62

6.52

7.95

10.1

13.4

19.9

29.3

432

53.1

59.2

60.3

58.7

55.7

52.9

49.6

42.4

36.6

31.3

26.7

15.3

5.10

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00:

0.00

0.00

0.00

0.00

0.01

0.01

0.01

0.01

0.02

0.02

0.03

0.04

0.12

0.50

1.07

2.53

4.70

8.55

16.9

23.9

32.2

38.8

46.1

50.0

54.9

62.6

68.8

74.2

78.9

91.7

107

0.00

0.00

0.02

0.03

0.04

0.05

0.06

0.08

0.10

0.12

0.15

0.48

1.13

2.45

4.52

8.83

14.3

21.8

28.8

35.6

41.5

46.0

50.7

60.1

67.3

73.7

79.0

92.4

106

0.00

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.71

1.68

2.69

5.31

8.55

16.4

19.3

19.0

17.4

15.7

13.8

12.6

10.8

7.71

7.03

5.92

5.05

2.77

0.06

0.00

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.36

1.68

2.94

5.35

9.00

14.7

18.3

19.6

18.6

16.7

14.8

13.4

12.0

9.75

8.23

6.99

5.91

3.01

0.10 ________ 1. A. J. 1. ________

1) All numeical values are presented at elevation vith peak power

G-155
[• indivi •Cha cs RefaricaI &d Fuel Rods"'

(Pre iyadiar j .ie dia~dedCladding)udrIRTss

Table G-8.6. Temperature Variation, Fission Gas Release and ZrO2 Thickness Vs. Time for Fuel

Rod #H8T Calculated by FRAP-T6 and SCANAIR Codes

-. Average Fuel centerline Fuel surface Clad outer 2) Time temperature ) temperature') temperature) Fission gas release ZrOt i 2

(s)K)K)() (0/) thickness

(K) _SIn) (K) (K) 

-. FRAP-T6 JSCANAIR FRAP-T6 _SCANAIR FRAP-T6 JSCANAIR FRAP-T6 jSCANAIR FRAP-T6

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

304

333

341

349

358

369

380

394

411

436

475

523

641

796

1001

1227

1361

1455

1485

1475

1451

1401

1240

1106

987

882

623

380

293

302

329

335

343

352

360

372

385

399

421

455

506

605

745

960

1133

1278

1353

1384

1380

1358

1318

1186

1056

931

825

574

375

293

302

327

334

342

350

359

369

381

397

417

446

478

547

628

642

620

615

596

576

553

545

545

591

575

565

552

493

378

293

301

325

331

338

346

354

364

376

389

409

437

476

546

633

724

751

738

712

684

661

646

631

605

585

563

541

469

373

293

297

316

321

327

334

342

351

360

372

383

389

393

401

409

422

426

425

423

421

418

416

413

407

405

403

401

393

376

293

297

314

318

324

331

337

345

354

364

37.7

381

384

389

394.

400

404

406

405

403

.401

399

398

395

393

391

389

,384

370

0.00

0.00

0.01

0.02

0.02

0.03

0.03

0.04

0.04

0.05

0.06

0.08

0.10

0.16

0.26

0.46

0.87

1.08

1.32

1.50

1.61

1.61

1.62

1.64

1.65

1.66

1.66

1.68

1.78

0.00

0.09

0.25

0.29

0.34

0.39

0.43

0.49

0.56

0.63

0.72

0.86

1.04

1.52

2.05

2.59

2.90

3.10

3.19

3.17

3.13

3.15

3.13

3.09

3.30

3.21

3.12

2.76

2.19

5

5

5

5

5

5

5

5.

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

1All numerical values are presented at elevation with peak power

2) Initial ZiO2 thickness is 5 tnn

G-156
#H8T I individualIa•iacterisfics of Refabricated Fuel Rods

-I (Preira dia tJ1,Preirradiated Cladding) under IGR Testi

Table G-8.7. Mechanical Characteristics of Fuel Rod #H8T Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes

Clad outer Fuel hoop Fuel - clad gap Clad hoop Clad hoop Internal gas Time temperature') strain1) width') strain') stressl) pressure (s) (K) (%) (mm) (%) (MPa) (MPa)

FRAP-T6TSCAN FRAP-T6 SCANAIR FRAP-T6 SCANAIR FRAP-T6 SCANAIR FRAP-T6 SCANAIR FRAP-T6 SCANAIR

0.0

*1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

297

316

321

327

334

342

351

360

372

383

389

393

401

409

422

426

425

423

421

418

416

413

407

405

403

401

393

376

293

297

314

318

324

331

337

345

354

364

377

381

384

389

394

400

404

406

405

403

401

399

398

395

393

391

389

384

370

0.00

0.01

0.05

0.06

0.07

0.08

0.09

0.11

0.12

0.15

0.18

0.23

0.29

0.44

0.65

0.94

1.26

1.44

1.54

1.60

1.56

1.47

1.35

1.10

0.92

0.77

0.65

0.36

0.10

0.00

0.01

0.02

0.03

0.03

0.04

0.05

0.05

0.06

0.07

0.09

0.12

0.15

0.22

0.33

0.51

0.63

0.71

0.72

0.69

0.65

0.60

0.55

0.45

0.37

0.30

0.25

0.12

0.01

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.02

0.02

0.02

0.01

0.00

0.00

.0.00

0.00

0.00

0.00

0.00

0.00

0.01

0.02

0.02

0.03

0.04

0.05

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.02

0.02

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.02

0.02

0.02

0.02

0.03

0.03

0.01

0.01

0.02

0.03

0.03

0.04

0.04

0.05 10.05

0.01

0.01

0.02

0.03

0.03

0.04

0.04

0.05 1 0.05

0.06

0.07

0.08

0.08

0.09

0.10

0.17

o.44

0.59

0.68

0.73

0.69

0.62

0.52

0.49

0.48

0.48

0A8

0.47

0.45

0.06

0.07

0.08

0.08

0.09

0.10

0.12

0.14

0.14

0.14

0.13

0.12

0.12

0.11

0.11

0.10

0.10

0.09

0.08

0.07

8.63

8.68

8.81

8.84

8.88

8.91

8.95

8.99

9.03

9.09

9.16

9.26

9.37

9.57

9.77

72.8

389

387

376

355

267

193

76.4

10.3

10.2

10.1

10.1

9.74

9.18

7.96

8.02

8.15

8.18

8.21

8.25

8.28

8.33

8.38

8.43

8.52

8.69

8.92

9.35

9.92

10.7

11.1

11.3

11.2

11.1

10.9

10.7

10.6

10.3

10.1

9.93

9.75

9.20

8.50

1.70

1.71

1.73

1.74

1.75

1.75

1.76

1.77

1.77

1.78

1.80

1.82

1.84

1.87

1.91

1.95

1.97

1.99

2.00

2.00

2.00

2.00

2.00

1.98

1.97

1.95

1.94

1.88

1.78

1.70

1.70

1.72

1.73

1.73

1.74

1.74

1.75

1.76

1.77

1.78

1.80

1.83

1.87

1.91

1.96

1.98

2.00

2.00

2.00

2.00

2.00

2.00

1.98

1.97

1.96

1.94

1.88

1.79

" All numerical values are presented at elevation %ith peak powcr

G-157
#H8T Individuil Ch6arcte6siics of Refabricated Fuel Rods . .

(Preirradiated FueLJ7 diated Cladding) under IGR Tests

Table G-8.8. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #H8T

Axial interval Energy deposition at infinite time Fuel enthalpy

from-to at time (t=5.16 s)

(mm)-(mm) cal/g fuel J/g fuel per-unit eal/g fuel J/g fuel per-unit

10.5-27.2 117 490 1.00 61.4 257 1.00

27.2-43.9 116 486 0.99 60.9 255 0.99

43.9-60.6 115 481 0.98 60.3 253 0.98

60.6- 77.3 110 461 0.94 57.8 242 0.94

77.3 - 94.0 110 461 0.94 57.8 242 0.94

94.0- 110.7 109 457 0.93 57.2 240 0.93

110.7 - 127.4 108 451 0.92 56.5 237 0.92

127.4 - 144.1 106 443 0.90 55.6 233 0.90

144.1 - 160.8 103 430 0.88 53.8 226 0.88

160.8- 177.5 99.6 417 0.85 52.3 219 0.85

120

c- 100

so

• •80

• 60

0

20 4 0

~20

... o... .... b.. . .. . .%

I Energy deposition

.... Fuel enthalpy

0

0 20 40 60 80 100

Axial coordinate (mm)

120 140 160 180

Fig. G-8.4. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6 Code

for Fuel Rod #H8T

G-158
#H8T Individual Ciariacteristics of Refabricated Fuel Rods

(PreirradiatA Fueý,.Preirradiated Cladding) under IGR Tests

1.2

U235

C>

0

I

1.0 -4 -..

.8 -1

0.6 -f--

IJ

IT :II

I

0.4

02. I _ -

I I I

1 2 3 4

Radial fuel coordinate (mm)

1.2

PU2 9

0

1.0

0.8

0.6

0.4

I I _______________ ___________

Hr

B

I II

0.2 -t-- - -Y- -

3

3 1 2 4

Radial fuel coordinate (mam)

Fig. G-8.5. U23 and Pu239 Radial Distributions of Energy Deposition for Fuel Rod #H8T

G-159
#H8T lndividual Charalcum iiAiseofRefabricated Fuel Rods

_(Preirradiated Fuei~c-Adiated Cladding) under IGR Tests

1.2

0

0

33,-

1.0 -

0.8-

0.6 -

0.4 -

+

I 4-

>1, II

Ill

0.2 I I

1 3

I

2 4

Radial fuel coordinate (mm)

90

80

70

60

50

. 40

W30

20

10

0

-- 2.Os

-- [3- 3.05s

________ ________ 0- 5.2s

1.0 1.5 2.0 2.5 3.0 3.5 4.0

Radial fuel coordinate (mm)

Fig. G-8.6. Radial Distributions of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #1H8T

G-160
#H8T A Individual tteristics of Refabricated Fuel Rods

I (Preirradia " JFG Preirradiated Cladding) "'der IGR Tests

180

150

ýi 120

60

120

100

80

60o

40 •

20

0

30

0

IWOV .

.0---000

0 1 2 3 4 5 6 7 8 9 10

Time (s)

1600

1200

20

.1

C)

2

C)

800

15 10

U

C0

5

r'

400

0 0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. G-8.7. Energy and Temperature Characteristics Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes for Fuel Rod #H8T

G-161
#H8T IndividulC 'arsat1tia ofRefabricated Fuel Rods

(Preirradiated Futel••q Wdiated Cladding) under IGR Tests.

2.50

2.00

2 1.50

I-V ~a1.00

E

0.50

0.00

0.80

0.60

. 0.40 0

0

7'3

0.20

0.00

*500

400

300

0.

200 ,.=

r0

100

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

0.04

I 0.

co

10

CI

Y)

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. G-8.8. Cladding Mechanical Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #H8T

G-162
#H8T lndiividuaiJ cteristics of Refabricated Fuel Rods I (Preiriadia t.i- ,Preirradiated Cladding) under IGR Tests -

2.0

1.6

1.2 W1

0

0.8

0.4

0.0

3.5

3.0

•"2.5

.• 2.0

1.5

1.0

1500

1200

900 v

E

600

300

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

0.5

0.0

0 1 2 3 4 5 7 8 9 10

Time (s)

Fig. G-8.9. Fuel Strain and Fission Gas Release Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #H8T

G-163
Individual Chariiacsteics of Refabricated Fuel Rods: R8T (Preirradiated Fuýlt.k'ei"adiated Cladding) under IGR Tests

Table G-8.9. Some Results of PIE for Fuel Rod #118T

Characteristic Value

I. Measured parameters of cladding oxidation and cladding

deformation

1.1. Cladding thickness at elevation 90 mm for different azimuthal

angles (pm):

00 705

900 705

1800 691

2700 691

1.2. Zr0 2 thickness at elevation 90 mm for different azimuthal angles

(gm):

00 5

900 5

1800 5

2700 5

1.3. atZr(O) thickness at elevation 90 mm for different azimuthal angles

(Pm):

00 0

900 0

1800 0

2700 0

1.4. Clad hoop strain at elevation 90 mm (%) 0

2. Measured parameters for FGR analysis

2.1. Internal gas composition (% by volume):

He 95.33

N2 0.1

02 0.02

Ar 0.004

C0 2 0.01

Kr 0.49

Xe 4.05

Free gas volume (cm3) 5.86

2.3. Gas pressure inside fuel rod under normal condition (MPa) 1.657

2.4. Kr concentration in fuel (cm3

/g fuel) 0.16

3. Measured parameters of cladding hydriding

3.1. Coefficient of hydride orientation (per-unit) 0.23

3.2. Hydrogen concentration (% by weight) 4 10-3

G-164
#H8T I Itndividuald•55-0cteristics of Refabricated Fuel Rods

(Preirradia reirradiated Cladding) under IGR'Tests,.

Table G-8.10. General Characteristic of Fuel Rod #H8T

Parameter Unit Value

Experiment FRAP-T6 SCANAIR

1 Type of coolant - water water water

2 Burnup MWd/kg U 46.8 46.8 46.8

3 Energy deposition in fuel rod cal/g fuel 109 109 109

4 Peak fuel enthalpy cal/g fuel - 61 60

5 Peak fuel temperature K - 1487 1386

6 Peak clad temperature K - 426 406

7 Fuel rod failure Yes, No No No 

P

8 Type of failure:

- cladding rupture due to ballooning Yes, No No No

- cladding rupture due to PCMI Yes, No No No

- fragmentation of fuel rod Yes, No No -

9 Failure time s -

10 Fuel enthalpy at failure calg fuel ' -

11 Outer cladding temperature at failure K - -

12 Internal gas pressure at failure MPa - -

13 ZrO2 thickness after test Pm 5 5.00 -

14 Residual clad hoop strain:

- peak value for ballooning area % - -

- other location1) % 0 0.26 0

15 Kr concentration in internal gas % by volume 0.49 0.10 0.36

composition after test

16 Xe concentration in internal gas % by volume 4.05 0.80 2.16 _ composition after test

17 Kr concentration in fuel after test cm3/g fuel 0.16 0.13 0.20

"Calculated values by FRAP-T6 and SCANAIR codes are average along height of fuel rod excluding ballooning region

G-165

IndividUalGd Iaracterstiksj orFuel 9Tuii4de IGR Test

G-167
#B9T JdiiýdM dýdtaChrte'n'sb'cslof abricatcd Fuel 'Rods-.

kPre'iriidiatcdFj! Fuei~dated Cl~dding) inder IGR Tests;-

1 Positionif (90')

Fig. G-9.1. Appearance of Fuel Rod #B9T (photographs and X-ray photograph)

G-168
#B9T

Position I

]divi~duaciterisflcs i of Refabricat&1 Fuel Rods~-_

:ýPr~irCadM PreiffadiatedCladddiiig)'u-nder IGR Tests :•:•]

SD

Fig. G-9.2. Cross-Section and Cladding Microstructure for Fuel Rod NB9T at 85 mm Elevation

G-169
#B9T Iridividdal dcharfterlstisfRcfabrictdFe os7

(Prcirýiadiatd FueL'torezaiated Claddinig) un'erd&GR.Tists.'

Position3

Fig. G-9.3. Cross-Section and Cladding Microstructure for Fuel Rod #B9T at 165 mm Elevation

G-170
#B9T I 1diidtW aaci~~ristics 0f Refbrcatýd F'u.elRodsi 1., , I md (Perai~~ rciuiadiit~d Claddindg) under- IGR Tests,,ý

Fig. G-9.4. Fuel Microstructure for Fuel Rod #B9T at 85 mm Elevation

G-171
#B9T (Preirra iated Fated Claddirig) tinder"IGR TeitS " . I

Table G-9.1. Time Dependent Energy Characteristics of Fuel Rod #B9T.

Reac- Cumulative number of fissions Power Energy

tor in fuel rod (fiss) of fuel deposition

Time energy rod in fuel rod

(s) deposi- O235 U238 

pu239 Pu24 Other Total (kW) cal/g J/g fuel

tbon') xl0-14 xIO-13 xlO"14 xl0"t 4 iso- x10"14 fuel

(%) jtopes

x10-11

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

9.0

10.0

20.0

30.0

00

0.000

0.929

6.340

8.860

12.30

17.30

24.80

36.80

53.50

67.70

77.20

83.20

87.10

89.60

91.40

92.60

93.50

94.10

94.60

95.00

95.40

95.70

95.90

96.40

96.70

97.00

97.20

97.60

97.90

99.10

99.60

100.0

0.000

0.035

0.241

0.337

0.469

0.658

0.942

1.400

2.030

2.570

2.930

3.160

3.310

3.410

3.470

3.520

3.550

3.580

3.600

3.610

3.620

3.640

3.640

3.660

3.680

3.690

3.690

3.710

3.720

3.770

3.780

3.820

0.000

0.017

0.117

0.164

0.228

0.320

0.458

0.680

0.989

1.250

1.430

1.540

1.610

1.660

1.690

1.710

1.730

1.740

1.750

1.760

1.760

1.770

1.770

1.780

1.790

1.790

1.800

1.800

1.810

1.830

1.840

1.860

0.000

0.065

0.441

0.616

0.858

1.200

1.720

2.560

3.720

4.700

5.370

5.790

6.050

6.230

6.350

6.440

6.500

6.540

6.580

6.610

6.630

6.650

6.670

6.700

6.720

6.740

6.760

6.780

6.800

6.890

6.920

6.980

0.000

0.025

0.173

0.242

0.337

0.473

0.677

1.000

1.460

1.850

2.110

2.270

2.380

2.450

2.500

2.530

2.550

2.570

2.590

2.600

2.610

2.610

2.620

2.630

2.640

2.650

2.660

2.670

2.670

2.710

.2.720

2.740

0.000

0.087

0.591

0.825

1.150

1.610

2.310

3.430

4.990

6.300

7.190

7.760

8.120

8.350

8.510

8.630

8.710

8.770

8.820

8.860

8.890

8.910

8.940

8.980:

9.010

9.040

9.060

9.090

9.120

9.240

0.000

0.127

0.867

1.210

1.690

2.370

3.390

5.030

7.320

9.250

10.60

11.40

11.90

12.30

12.50

12.70

12.80

12.90

12.90

13.00

13.00

13.10

13.10

13.20

13.20

13.30

13.30

13.30

13.40

13.60

13.60

13.70

0.000

0.815

4.210

5.770

8.070

11.80

18.20

29.70

32.20

23.10

14.90

9.470

6.160

4.160

2.910

2.110

1.580

1.220

0.964

0.787

0.670

0.576

0.501

0.368

0.287

0.236

0.201

0.173

0.139

0.000

1.480

10.10

14.10

19.70

27.60

39.50

58.60

85.30

108.0

123.0

133.0

139.0

143.0

146.0

148.0

150.0

151.0

152.0

152.0

153.0

153.0

154.0

155.0

155.0

156.0

156.0

157.0

158.0

0.000

6.200

42.30

59.00

82.50

116.0

165.0

245.0

357.0

452.0

515.0

557.0

582.0

599.0

611.0

620.0

628.0

632.0

636.0

636.0

640.0

640.0

645.0

649.0

649.0

653.0

653.0

657.0

661.0

670.0

674.0

691.0

0.036 '1 160.0

9.280

9.360

0.019

0.000

161.0

165.0 I * .3. U L a a a

Maximum value of power is 34.2 kW (t - 3.10 s).

1) Current energy deposition per maximum energy deposition (at infinite time)

G-172
#B9T Oii adaL 'ti Rfabric~tea Fuel1 Ro~ds K

__ e rimdadCladding') under IGR Tests'..

Table G-9.2. Axial Energy Characteristics of Fuel Rod #B9T

Axial Cumulative number of fissions Maxi- Energy deposition

coordi- at axial interval (fiss) mum at infinite time*

fater U U23 8 pu2 3 9 pu

24 O r powerof from Other Total ro cal/g J/g perlower x10- X10X' ×1 0" 3 X10"3 iso- x10"13 fuel rod fuel fuel unit 3

)

end of topes t3.10s

fuel rod x1010 t

(mm) I I I I I

10.0

15.0

20.0')

25.0

30.0

35.0

40.0

45.0

50.0

55.0

60.0

65.0

70.0

75.0

80.0

85.0

90.0

95.0

100.0

105.0

110.0

115.0

120.0

125.0

130.0

135.0

140.0

145.0

150.0

155.0

160.0

165.0

170.02)

175.0

180.0

185.0

0.000

0.000

.0.646

1.310

1.340

1.340

1.290

1.250

1.250

1.260

1.260

1.260

1.310

1.350

1.340

1.330

1.330

1.310

1.300

1.280

1.300

1.330

1.350

1.370

1.370

1.360

1.380

.1.420

1.370

1.380

0.727

0.727

0.364

0.000

0.000

0.000

0.000

0.000

3.230

6.550

6.560

6.460

6.490

6.480

6.420

6.400

6.380

6.350

6.300

6.260

6.260

6.280

6.300

6.320

6.370

6.440

6.490

6.530

6.570

6.640

6.650

6.570

6.520

6.510

6.450

6.700

3.270

3.270

1.640

0.000

0.000

0.000

0.000

0.000

1.210

2.450

2.460

2.430

2.420

2.410

2.390

2.380

2.380

2.370

2.370

2.370

2.360

2.370

2.370

2.380

2.390

2.410

2.430

2.450

2.470

2.490

2.500

2.470

2.450

2.460

2.430

2.510

1.300

1.300

0.648

0.000

0.000

0.000

0.000

0.000

0.476

0.966

0.967

0.951

0.958

0.959

0.950

0.945

0.943

0.937

0.928

0.919

0.920

0.000

0.000

1.480

3.040

3.110

3.180

3.230

3.270

3.300

3.320

3.330

3.330

3.320

3.320

3.300

3.290

3.270

3.250

3.230

3.220

3.200

3.190

3.190

3.200

3.210

3.230

3.260

3.310

3.370

3.440

0.925

0.927

0.932

0.940

0.951

0.958

0.964

0.971

0.979

0.980

0.970

0.958

0.956

0.949

0.988

0.506

0.506

0.253

0.000

0.000

2.360

4.800

4.830

4.780

4.740

4.680

4.650

4.650

4.650

4.630

4.670

4.700

4.690

4.680

4.690

4.690

4.690

4.700

4.760

4.810

4.850

4.910

4.920

4.860

4.860

4.900

4.820

4.950

2.560

2.560

1.280

0.000

0.000

0.000

0.000

0.000

0.588

1.190

1.200

1.190

1.180

1.170

1.160

1.160

1.160

1.150

1.160

1.170

1.170

1.170

1.170

1.170

1.170

1.170

1.180

1.200

1.210

1.220

1.220

1.210

1.210

1.220

1.200

1.230

0 .637

0.637

0.319

0.000

0.000

0.000

0.000

0.000

164.0

164.0

164.0

165.0

163.0

162.0

162.0

163.0

163.0

163.0

165.0

167.0

167.0

166.0

166.0

166.0

165.0

163.0

164.0

164.0

165.0

165.0

165.0

165.0

166.0

168.0

166.0

165.0

168.0

168.0

168.0

0.000

0.000

0.000

0.000

0.000

687.0

687.0

687.0

691.0

682.0

678.0

678.0

682.0

682.0

682.0

691.0

699.0

699.0

695.0

695.0

695.0

691.0

682.0

687.0

687.0

691.0

691.0

691.0

691.0

.695.0

703.0

695.0

691.0

703.0

703.0

703.0

0.000

0.000

0.000

0.00

0.00

0.98

0.98

0.98

0.98

0.97

0.96

0.96

0.97

0.97

0.97

0.98

0.99

0.99

0.99

0.99

0.99

0.98

0.97

0.98

0.98

0.98

0.98

0.98

0.98

0.99

1.00

0.99

0.98

1.00

1.00

1.00

0.00

0.00

0.00

1.670

1.670

0.837

0.000

0.000

0.000

0.000

0.000

0.000

All numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate t 2.5 mm

I) Initial coordinate of fuel is 20.0 mm

2) End coordinate of fuel is 170.0 mm

3) Current value per maximum value.

G-173
#B9T ldiiual Chaiictensti& VfRefabrictdFe O1

Prirradiae FuLri~dae ldg) n& IGR Tests

Table G-9.3. Radial Energy Characteristics of Fuel Rod #B9T

Coordinates of fuel zones (mm)

Characteristics* I zone 2 zone 3 zone 4 zone

1.2- 2.811 2.811-3.432 3.432-3.704 3.704-3.790

Number of fissions X 10"14 (fiss) 1.850 1.080 0.528 0.171

Power of fuel rod') (kW) 4.520 2.640 1.290 0.418

U23 5 Energy deposition2) (cayg fuel) 45.70 44.50 43.40 42.20

Energy deposition2 ) (J/g fuel) 191.0 186.0 182.0 177.0

Energy deposition3) (per-unit) 1.000 0.974 0.950 0.923

Number of fissions xl0- 2 (fiss) 9.160 5.290 2.520 0.778

Power of fuel rod') (kW) 0.221 0.128 0.061 0.019

u 23 Energy deposition2 ) (callg fuel) 2.230 2.140 2.040 1.890

Energy deposition 2) (J/g fuel) 9.330 8.960 8.540 7.910

Energy deposition3) (per-unit) 1.000 0.960 0.915 0.848

Number of fissions x 10"14 (fiss) 2.770 1.880 1.280 0.724

Power of fuel rod') (kW) 6.980 4.730 3.230 1.820

Put23 Energy deposition2) (cal/g fuel) 70.80 80.00 109.0 185.0

Energy deposition2) (J/g fuel) 296.0 335.0 456.0 774.0

Energy deposition3) (per-unit) 0.383 0.432 0.589 1.000

Number of fissions x 10"t (fiss) 10.40 7.360 5.260 3.120

Power of fuel rod') (kW) 2.580 1.820 1.300 0.773

Pu24 1 Energy deposition2) (cal/g fuel) 26.10 30.80 44.00 78.40

Energy deposition2) (J/g fuel) 109.0 129.0 184.0 328.0

Energy deposition3) (per-unit) 0.333 0.393 0.561 1.000

Number of fissions x 0I"W (fiss) 4.090 2.590 1.540 0.727

Other Power of fuel rodt) (kW) 0.010 0.006 0.004 0.002

isoto- Energy deposition2 ) (callg fuel) 0.103 0.109 0.129 0.184

pes Energy deposition2) (J/g fuel) 0.430 0.460 0.540 0.770

I Energy deposition3) (per-unit) 0.560 0.592 0.701 1.000

Number of fissions Xi10"14 (fiss) 5.760 3.750 2.370 1.220

Power of fuel rod') (kW) 14.30 9.340 5.890 3.030

Total Energy deposition2 • (cal/g fuel) 145.0 157.0 198.0 306.0

Energy deposition 2

) (J/g fuel) 607.0 657.0 829.0 1281.

Energy deposition 3

) (per-unit) 0.474 0.513 0.647 1.000

1) attime of3.10 s, 2) at infinite time. 3) Current value per maximum value.

* All numerical values of characteristics were calculated for undamaged part of fuel stack only (See Table C.2.2.)

G-174
#B9T -I 'rxdividuA Vreinstics 0 fabricgtede- i•Tst ;1

1ffiirrdiýeILrciiradiated Cladding) under JOR -Tests.-,-,.

Table G-9.4. Fuel Enthalpy Vs. Time Calculated by FRAP-T6 Code for Fuel Rod #B9T

Time Enthalpy at fuel raius I Fu el enthalpy'1 Energy deposition

(cal/ fuel) entha l l) IFel in fuel rod

(s) 1.20num 2.82 mm 3.47 mm 3.79 mm c/g fuel IJ/gfuel I cal/g fucl J/gfuel

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

1.30

5.48

6.95

9.19

13.3

21.5

37.1

59.9

84.4

103

116

123

127

130

131

131

130

130

129

129

128

127

125

123

121

119

114

83.1

0.00

1.27

5.25

6.66

8.85

12.9

21.0

36.2

58.1

80.3

96.4

105

110

113

115

117

118

118

118

118

118

117

117

116

115

114

113

110

81.7

0.00

1.21

4.95

6.28

8.34

12.1

19.5

33.1

50.0

68.9

80.8

87.3

92.4

100

104

106

108

109

109

109

110

110

110

110

110

109

109

106

80.3

0.00

1.13

4.67

5.93

7.83

11.2

17.4

28.6

38.2

56.4

65.4

73.4

85.1

94.8

98.7

101

102

104

104

105

105

106

106

106

107

106

106

104

79.5

0.00

1.26

5.22

6.63

8.79

12.7

20.6

35.3

55.7

77.6

93.2

103

109

113

116

118

119

119

119

119

119

118

117

116

115

114

o10

81.7

0.00

5.28

21.9

27.8

36.8

53.3

86.4

148

233

325

391

430

455

475

487

493

497

498

498

498

497

495

494

489

485

480

476

460

342

0.00

1.57

6.68

8.43

11.1

15.7

24.7

41.6

66.0

91.7

111

124

133

139

142

145

147

149

150

151

152

153

153

154

155

156

156

158

161

0.00

6.58

28.0

35.3

46.3

65.6

104

174

276

384

467

521

557

580

597

608

617

625

630

633

637

640

642

646

650

652

654

660

674

Radial enthalpy distribution and fuel enthalpy are presented at elevation 162.5 rmn

Maximum value of fuel enthalpy is 118.9 cal/g fuel (t-5.11 s)

') All numerical values are presented at elevation with peak povcr

G-175
#B9T I(Preirr'diated F Mi~Jein"diated Cladding) ,indke IGR Tests.I

Table G-9.5. Energy Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel

Rod #B9T

Tie Energy Linear 1)) Clad-to-coolant heat

Time Eergyinpower ) Fuel enthalpy1 ( s) (cal/g fuel) ) Leakage .o(capg of fuel) energy' transfer coefficient')

(cal/g fuel) (kW/m) (kfuV/mK)

FRAP-T6 _JSCANAIR FRAP-T6_SAAIR FRAP-T6 ISCANAIR

0.0

1.0

2.0

2.2

2A

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

1.60

6.78

8.56

11.2

15.9

25.1

422

67.0

93.1

113

126

135

141

145

147

149

151

153

154

154

155

156

157

157

158

159

160

164

0.00

5.90

13.5

18.5

29.9

56.3

112

191

238

210

144

93.4

61.1

41.3

29.0

21.2

16.0

11.6

9.48

7.78

6.35

5.36

4.58

3.22

2.41

1.92

1.60

1.06

0.14

0.00

1.26

5.22

6.63

8.79

12.7

20.6

35.3

55.7

77.6

93.2

103

109

113

116

118

119

119

119

119

119

118

118

117

116

115

114

110

81.7

0.00

1.48

5.78

7.33

9.77

14.3

23.4

39.3

60.4

79.9

92.8

0.00

0.00

0.00

0.01

0.01

0.01

0.02

0.03

0.05,

0.10

0.21

0.36

0.55

0.80

1.07

137

1.71

2.18

2.56

.2.98

3.43

3.91

4.39

5.70

7.06

8.42

9.88

15.5

55.3

0.00

0.00

0.00

0.01

0.01

0.01

0.02

0.03

0.06

0.13

0.27

0.00

0.01

0.01

0.01

0.01

0.01

0.01

0.02

0.03

0.04

0.05

0.06

0.07

0.08

0.08

0.09

0.09

0.10

0.10

0.11

0.11

0.11

0.12

0.12

0.12

0.13

0.13

0.12

0.08

* 0.00

0.01

0.01

0.01

0.01

0.01

0.01

0.02

0.03

0.04

0.06

1) All nwumrical values are presented at elevation ith peak poyer

G-176
#B9T I Inivdu ir~~istics of Refabricaied Fuel Rods

~(Preir adiit reiradiated Cliddinj) uiidei IGR et

Table G-9.6. Temperature Variation, Fission Gas Release and ZrO2 Thickness Vs. Time for Fuel

Rod #B9T Calculated by FRAP-T6 and SCANAIR Codes

Fuel centerline Fuel surface Clad outer Fission gas release

Tim temperaturel) temperature1) temperature) (%)

(s) (K) (K) .(K)_ __ _

FRAP-T6 I SCANAIR FRAP-T6 SCANAIR FRAP-T6 I SCANAIR FRAP-T6 I SCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

316

385

408

443

504

624

840

.1145

1460

1695

1843

1930

1979

2004

2014

2016

2012

2007

2000

1991

1982

1973

1948

1925

1903

1883

1820

1445

293

318

387

412

449

516

646

867

1153

1424

1614

293

313

372

392

422

473

565

724

855

1098

1217

1320

1469

1591

1639

1667

1684

1700

1707

1714

1720

1724

1728

1734

1735

1734

1729

1703

1399

293

315

378

400

434

495

607

784

987

1161

1267

293

302

346

360

380

409

465

565

755

934

1082

1170

1266

1299

1338

1376

1412

1452

1477

1501

1521

1538

1552

1578

1593

1601

1605

1595

1329

293

304

351

367

389

424

490

610

791

998

1146

0.00

0.02

0.11

0.14

0.19

0.28

0.48

0.96

1.87

3.29

4.17

4.67

4.98

5.23

5.45

5.62

5.74

5.95

8.08

9.24

9.70

10.1

10.4

11.7

13.6

13.8

13.8

13.9

14.4

0.00

0.19

0.61

0.73

0.90

1.14

1.61

2.16

2.71

3.13

3.38

A. A. I I I I A.

1) All numerical values are presented at elevation with peak power

G-177
#B9T ddiaividu1lc6 a~~ ~earctdFelRd sc

ý(PreirradiatedFue! ,iZdiated Cladding)wi~derI]GRýT's'ts*,,

Table G-9.7. Mechanical Characteristics of Fuel Rod #1B9T Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes

Clad outer Fuel hoop Fuel - clad gap Clad hoop Clad hoop Internal gas (s) temperature') strain') width') strain') stressi) pressure

___(K) (%) (mm) M) (MPa) (MPa)

FRAP.T61SCANAI FRAP-T61 SCAN FRAP-T6 ISCAN FRAP-T6 SC__ FRAP-T61SCANAI FRAP-T6[SCANAlR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

302

346

360

380

409

465

565

755

934

1082

1170

1266

1299

1338

1376

1412

1452

1477

1501

1521

1538

1552

1578

1593

1601

1605

1595

1329

293

304

351

367

389

424

490

610

791

998

1146

0.00

0.04

0.15

0.18

0.24

0.33

0.52

0.86

1.36

1.94

2.36

2.61

2.79

2.97

3.07

3.15

3.20

3.33

3.67

3.93

4.07

4.20

4.20

4.36

4.52

4.46

4.39

4.11

2.45

0.00

0.02

0.07

0.08

0.11

0.16

0.27

0.47

0.76

1.06

1.28

0.03

0.03

0.03

0.02

0.02

0.02

0.01

0.00

0.00

0.00

0.00

0.00

0.11

1.74

1.74

1.74

1.73

1.73

1.72

1.71

1.70

1.70

1.70

1.69

1.68

1.69

1.69

1.70

1.76

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.02

0.02

0.01

0.00

0.01

0.01

0.04

0.05

0.07

0.09

0.13

0.20

0.55

1.05

1.42

1.62

4.15

46.5

46.6

46.6

46.6

46.7

46.7

46.7

46.7

46.8

46.8

46.8

46.8

46.8

46.8

46.8

46.6

0.01

0.02

0.05

0.06

0.08

0.11

0.16

0.25

0.40

0.56

0.54

8.38

8.49

8.73

8.80

8.89

9.02

9.23

9.49

228

40.8

20.8

9.43

10.7

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

8.25

8.38

8.66

8.74

8.85

9.04

9.34

9.68

9.92

9.98

9.73

1.70

1.72

1.77

1.78

1.80

1.82

1.86

1.91

1.96

2.00

2.03

2.05

2.04

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

1.70

1.72

1.77

1.78

1.80

1.83

1.87

1.92

1.95

1.98

1.99

1) All numerical values are presented at elevation %%ith peak poxwr

G-178
#B9T Iluidhvidtiý rsiso efbie ulRd

rerr at Cladding) týine IGR T's~ts.'',

Table G-9.8. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod 0B9T

Axial interval Ener deposition at infnite time Fuel enthalpy

from-to Enrydpsto at time (t=5.11 s)

(mm)-(mm) cavg fuel J/g fuel per-unit cal/g fuel Jig fuel per-unit

20.0-35.0 164 688 0.98 117 488 0.98

35.0-50.0 163 682 0.97 116 484 0.97

50.0- 65.0 163 682 0.97 116 484 0.97

65.0- 80.0 166 694 0.99 118 493 0.99

80.0-95.0 166 696 0.99 118 494 0.99

95.0- 110.0 164 689 0.98 117 489 0.98

110.0 - 125.0 165 689 0.98 117 489 0.98

125.0 - 140.0 165 692 0.99 117 491 0.99

140.0 - 155.0 167 698 0.99 118 495 0.99

155.0 - 170.0 168 702 1.00 119 498 1.00

Cu

c-Cu

0=

0 30 60 90 120 150 180

Axial coordinate (mm)

Fig. G-9.5. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6 Code

for Fuel Rod #B9T

G-179
#B9T ]ndididu - CharaiSfRefabrncated h'a6 FUel Rods '

('eii'radiatoi1 _foi~ited Cladding)tuinder IGR-Tests

1.2

0

1.0 -

0.8 -

t

A

0.6 -1-

u235

J 11 V

0.'4

0.2 .4 -

I I

I 2 3 4

Radial fuel coordinate (mm)

1.2

U

C,

1.0

0.8

0.6

0.4

0.2

2 3 4

Radial fuel coordinate (mm)

Fig. G-9.6. U235 and Pu 239Radial Distributions of Energy.Deposition for Fuel Rod #B9T

G-180
#B9T I __d____n of Refabricated Fuel Rods

I Prirad~flF1.rerrdat cd C I a~ddýit)-nde'r'IG'R Tes-ts'-*'-

1.2

i

I.'

0U

1.0

0.8

0.6

Jý

0.4 -j- .~

4 I

0.2 g _ - - I I I 1 I

1 2 3 4

Radial fuel coordinate (mm)

150

120

f-.

(3U

C-

(.3

90

60

30

0

1.0 1.5 2.0 2.5 3.0 3.5

Radial fuel coordinate (mm)

4.0

Fig. G-9.7. Radial Distributions of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #B9T

G-181
#B9T I idividu -al'C h s if Reifabr ic d Fuel R o d S • I! : I

,,(Preirradiated Fuýid,* inated Cladding) iin'der IGR Tests::.,"-

250

200

E

10050

0

200

160

120 ,-

80 TO

40

0

0 1 2 3 4 5 6 7 8 9 .10

Time (s)

2500

2000

.- 1500

U

E 1000

5-0

500

0

0.15

0

0.09N0. 0 3-

0.00

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. G-9.8. Energy and Temperature Characteristics Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes for Fuel Rod #B9T

G-182
#B9T Indiv2d i• istics of Refabrik(ýed Fuei Rods' •(~ ~ • '• rirdae Claddinig) unlder IGR-Tests.•:' "

2.5

2.0

2 1.5

- 1.0

E

0.5

0.0

50,

40

30

0

20-

10

0

250

200

150

Ca 0

100 '-

U

50

0

2.0

1.6

E

1.2 "

C-

"0

0.8 .

U

0 1. 2 3 .4 5 6 7 8 9 10

Time (s)

0.4

0.0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. G-9.9. Cladding Mechanical Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #1B9T

G-183
#B9T IndividualAM~she)f Refabricated, Fue I Rod ' -.

(Preirm~diatcd Nc~iW'MzrýaWiad Cladding) )under GRýe

5

4

0

2

0

2500

2000

1500

E

1000 "

U

500

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

15

12

LT.

0 1 2 3 4 5

Time (s)

6 7 8 9 10

Fig. G-9.10. Fuel Strain and Fission Gas Release Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #B9T

G-184
#B9T I Iidiiiduial'Chrteis 1ic of Ref'abrkted.FuelR

(Pirie h ~ rirridiafed Ciaddinj)Viide'r'IGRTci

Table G-9.9. Some Results of PIE for Fuel Rod #B9T

Characteristic Value

1. Measured parameters of cladding oxidation and cladding

deformation

1.1. Cladding thickness at elevation 85, 165 mm correspondent to

different azimuthal angles (pm):

00 649 649

900 649 R

1800 649 580

2700 649 620

1.2. ZrO2 thickness at elevation 85, 165 mm correspondent to different

azimuthal angles (prn):

00 10 10

900 10 10

1800 10 10

2700 10 10

1.3. c.Zr(O) thickness at elevation 85, 165 mm correspondent to

different azimuthal angles (pm):

00 10 10

900 10 10

1800 10 10

2700 10 10

1.4. Clad hoop strain at elevation 85, 165 mm, respectively (%) 7.3 42.3

2. Measured parameters for FGR analysis

2.1. Internal gas composition (% by volume):

He

N2'

02

Ar

CO2

Kr

Xe

2.2. Free gas volume (cm3)

2.3. Gas pressure inside fuel rod under normal condition (MPa)

2.4. Kr concentration in fuel (cm 3

/g fuel)

3. Measured parameters of cladding hydriding

3.1. Coefficient of hydride orientation (per-unit)

3.2. Hydrogen concentration (% by weight)

G-185
#B9T Ienrdiatidu Chrc fearcae ul o s. (Peraitekui~ iated Cladding ne G et

Table G-9.10. General Characteristic of Fuel Rod #B9T

Parameter Unit Value

Experiment FRAP-T6 SCANAIR

1 Type of coolant -- air air air

2 Burnup MWd/kg U 49.7 49.7 49.7

3 Energy deposition in fuel rod cal/g fuel 165 165 165

4 Peak fuel enthalpy cal/g fuel - 119

5 Peak fuel temperature K - 2016

6 Peak clad temperature K - 1606

7 Fuel rod failure Yes, No Yes Yes

8 Type of failure:

- cladding rupture due to ballooning Yes, No Yes Yes

- cladding rupture due to PCMI Yes, No No No

- fragmentation of fuel rod Yes, No No - -

9 Failure time s - 3.96 -

10 Fuel enthalpy at failure callg fuel - 109 -

11 Outer cladding temperature at failure K 1266 -

12 Internal gas pressure at failure MPa - 2.04 -

13 ZrO2 thickness after test urm 10 - -

14 Residual clad hoop strain: _

- peak value for ballooning area % 42.3 46.20 -

- other locationi) % 7.3 4.57 -

15 Kr concentration in internal gas % by volume - 1.44 - composition after test

Xe concentration in internal gas 16 composition after test % by volume __-_8.65_-

17 Kr concentration in fuel after test cm3

/g fuel 0.11

')Calculated values by FRAP-T6 and SCANAJR codes are average along height of fuel rod excluding ballooning region

G-186
$ C-so.

kersticf

2

'rue B

O• ude CR• es•••t'$:-

G-187
#B1OT individual Chiract e ¢ of Refabricatcd Fuel Rods

(Preirradiated Fuýd&"E*'diated Cladding) under'IGR Tests

Positionm (90W)

Fig. G-10.1. Appearance of Fuel Rod #1B10T (photographs and X-ray photograph)

G-188
#B1OT

Position 2

Fig. G-10.2. Cross-Section and Cladding Microstructure for Fuel Rod #B1OT at 38 mm Elevation

G-189
#B1OT

Fig. G-10.3. Cross-Section and Cladding Microstructure for Fuel Rod #B10T at 98 mm Elevation

G-190
#B1OT Icd CladdiiOigiindcirlGiTicsts

Fig. G-10.4. Fuel Microstructure for Fuel Rod #B10T at 38 mm Elevation

G-191
#B1OT 'I~ndividudMal C1 sucis¶i Rcfabii'ca-tcd 4F-uý*l R-od#s"':"ýý;''

(PrerradattafeI~~~tftcdCladding) unider.IGRTet I

Table G-10.1. Time Dependent Energy Characteristics of Fuel Rod #B10T

Reac- Cumulative number of fissions Power Energy

tor in fuel rod (fiss) of fuel deposition

Time energy rod in fuel rod

(s) deposi- U2 3 U23 5 pu23 9 Pu24

l Other Total (kW) cal/g J/g fuel

ltion x10 14 xlO"13 xl0o1 4 xl0"14 iso- X10" 14 fuel

(%) Jtopes X100"

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

.7.0

7.5

8.0

9.0

10.0

20.0

30.0

0o

0.000

1.100

4.820

6.310

8.640

12.70

20.30

33.40

50.60

65.80

75.90

82.20

86.20

88.80

90.60

91.90

92.80

93.60

94.20

94.70

95.00

95.40

95.60

96.20

96.60

96.80

97.10

97.50

97.80

99.10

99.60

100.0

0.000

0.044

0.191

0.251

0.343

0.505

0.808

1.330

2.010

2.620

3.020

3.270

3.430

3.530

3.600

3.650

3.690

3.720

3.740

3.760

3.780

3.790

3.800

3.820

3.840

3.850

3.860

3.880

3.890

3.940

3.960

3.990

0.000

0.014

0.061.

0.079

0.109

0.160

0.256

0.421

0.638

0.829

0.956

1.040

1.090

1.120

1.140

1.160

1.170

1.180

1.190

1.190

1.200

1.200

1.210

1.210

1.220

1.220

1.220

1.230

1.230

1.250

1.250

1.270

0.000

0.060

0.264

0.346

0.473

0.697

1.110

1.830

2.770

3.600

4.160

4.500

4.720

4.870

4.960

5.040

5.090

5.130

5.160

5.190

5.210

5.230

5.240

5.270

5.290

5.310

5.320

5.340

5.360

5.430

5.460

5.500

0.000

0.021

0.093

0.122

0.167

0.245

0.393

0.645

0.977

1.270

1.470

1.590

1.660

1.710

1.750

1.770

1.790

1.810

1.820

1.830

1.840

1.840

1.850

1.860

1.860

1.870

1.870

1.880

1.890

1.910

1.920

1.940

0.000

0.066

0.287

0.376

0.514

0.757

1.210

1.990

3.010

3.920

4.520

4.890

5.130

5.290

5.400

5.470

5.530

5.570

5.610

5.640

5.660

5.680

5.700

5.730

5.750

5.770

5.780

•5.810

5.820.

5.900

5.930

5.980

0.000

0.127

0.555

0.727

0.995

1.460

2.340

3.850

5.830

7.580

8.740

9.470

9.930

10.20

10.40

10.60

10.70

10.80

10.80

10.90

10.90

11.00

11.00

11.10

11.10

11.20

11.20

11.20

11.30

11.40

.11.50

i 1.60

0.000

0.727

2.060

2.990

4.910

9.010

16.70

26.20

28.70

20.80

13.10

8.220

5.340

3.620

2.570

1.900

1.450

1.150

0.929

0.762

0.645

0.550

0.474

0.342

0.262

0.212

0.179

0.153

0.122

0.031

0.016

0.000

0.000

1.550

6.800

8.910

12.20

18.00

28.70

47.10

71.40

92.90

107.0

116.0

122.0

126.0

128.0

130.0

132.0

133.0

134.0

134.0

135.0

135.0

136.0

137.0

137.0

138.0

138.0

139.0

140.0

142.0

143.0

146.0

0.000

6.490

28.50

37.30

51.10

75.30

120.0

197.0

299.0

389.0

448.0

486.0

511.0

527.0

536.0

544.0

553.0

557.0

561.0

561.0

565.0

565.0

569.0

573.0

573.0

578.0

578.0

582.0

586.0

594.0

599.0

611.0 U I £ I A. A A. - U

Maximum value of power is 29.3 kW (t - 3.15 s).

I) Current energy deposition per maximum energy deposition (at infinite time)

G-192
#B10T lndics of Refabrfcated Fuel Rods, .

I: (Pte• • erradiated Cladding) tinder IGR !Tet

Table G-10.2. Axial Energy Characteristics of Fuel Rod #B10T

Axial Cumulative number of fissions Maxi- Energy deposition

coordi- at axial interval (fiss) mum at infinite time*

nate u235 u239 p29 u4of

from Pu2 9 Put"' Other Total power cal/g J/g perlower XI0-13 X10 X10-1 X10-1 iso_ X1013 fuel rod fuel fuel unit3

e

end of topes 3)15s

fuel rod xl0-10

(mm)

10.0

15.0

20.0

25.0')

30.0

35.0

40.0

45.0

50.0

55.0

60.0

65.0

70.0

75.0

80.0

85.0

90.0

95.0

100.0

105.0

110.0

115.0

120.0

125.0

130.0

135.0

140.0

145.0

150.0

155.0

160.0

165.0

170.0

175.02)

180.0

185.0

0.000

0.000

0.000

0.662

1.320

1.320

1.380

1.450

1.540

1.620

1.700

1.650

1.610

1.600

1.590

1.530

1.490

1.450

1.410

1.410

1.410

0.000

0.000

0.000

2.000

4.010

4.010

4.540

4.700

4.920

4.940

4.960

4.990

4.970

4.930

4.880

4.820

4.750

4.700

4.650

4.610

4.600

4.580

4.560

4.580

4.600

4.600

4.530

2.900

2.900

2.900

2.900

2.610

2.610

0.261

0.000

0.000

0.000

0.000

0.000

0.909

1.820

1.820

1.940

2.010

2.110

2.130

2.150

1.410

1.410

1.400

1.400

1.380

1.350

0.901

0.901

0.901

0.901

0.868

0.868

0.087

0.000

0.000

2.150

2.140

2.120

2.100

2.070

2.040

2.010

1.990

1.970

1.970

1.970

1.960

1.960

1.970

1.970

1.940

1.280

1.280

1.280

1.280

1.270

1.270

0.127

0.000

0.000

0.000

0.000

0.000

0.324

0.648

0.648

0.688

0.711

0.742

0.735

0.731

0.740

0.742

0.735

0.729

0.721

0.715

0.711

0.703

0.697

0.696

0.694

0.690

0.695

0.697

0.698

0.691

0.465

0.465

0.465

0.465

0.451

0.451

0.045

0.000

0.000

0.000

0.000

0.000

0.972

1.940

1.940

2.170

2.170

2.180

2.180

2.190

2.190

2.200

2.210

2.220

2.220

2.230

2.230

2.240

2.240

2.240

2.240

2.230

2.230

2.220

2.210

2.200

1.410

1.410

1.410

1.410

1.350

1.350

0.135

0.000

0.000

0.000

0.000

0.000

1.920

3.830

3.830

4.060

4.220

4.440

4.530

4.630

4.600

4.540

4.510

4.480

4.380

4.290

4.220

4.150

4.120

4.130

4.120

4.100

4.110

4.110

4.100

4.030

2.680

2.680

2.680

2.680

2.620

2.620

0.262

0.000

0.000

0.000

0.000

0.000

0.485

0.970

0.970

1.030

1.070

1.120

1.150

1.170

1.160

1.150

1.140

1.130

1.110

1.090

1.070

1.050

1.040

1.040

1.040

1.040

1.040

1.040

1.040

1.020

0.678

0.678

0.678

0.678

0.663

0.663

0.066

0.000

0.000

0.000

0.000

0.000

157.0

157.0

157.0

144.0

145.0

146.0

148.0

150.0

149.0

147.0

148.0

148.0

147.0

146.0

145.0

144.0

144.0

145.0

145.0

145.0

144.0

144.0

144.0

143.0

142.0

142.0

142.0

142.0

139.0

139.0

139.0

0.000

0.000

0.000

0.000

0.000

657.0

657.0

657.0

603.0

607.0

611.0

620.0

628.0

624.0

615.0

620.0

620.0

615.0

611.0

607.0

603.0

603.0

607.0

607.0

607.0

603.0

603.0

603.0

599.0

594.0

594.0

594.0

594.0

582.0

582.0

582.0

0.000

0.000

0.00

0.00

0.00

1.00

1.00

1.00

0.92

0.92

0.93

0.94

0.96

0.95

0.94

0.94

0.94

0.94

0.93

0.92

0.92

0.92

0.92

0.92

0.92

0.92

0.92

0.92

0.91

0.90

0.90

0.90

0.90

0.89

0.89

0.89

0.00

0.00

All numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate :: 2.5 mm

1) Initial coordinate of fuel is 25.0 mm.

2) End coordinate of fuel is 173.0 nun.

3) Current value per maximum value.

G-193
#B1OT izdividuaskc 4 Rhrcesi~ fabriat'id Fuel Rods'.-

I (Preir6di atefi Wir'iae Clding uner IRTss,

Table G-10.3. Radial Energy Characteristics of Fuel Rod #B10T

Coordinates of fuel zones (mm)

Characteristics* I zone 2 zone 3 zone 4 zone

1.2- 2.811 2.811-3.432 3.432-3.704 3.704-3.790

Number of fissions x10-14 (fiSS) 1.580 0.932 0.459 0.150

Power of fuel rod') (kW) 3.930 2.320 1.140 0.372

U235 Energy deposition2) (caVg fuel) 50.30 49.50 48.70 47.70

Energy deposition 2

) (J/g fuel) 211.0 207.0 204.0 200.0

Energy deposition 3

) (per-unit) 1.000 0.984 0.968 0.948

Number of fissions x10"2 (fiss) 5.140 2.960 1.400 0.435

Power of fuel rod') (kW) 0.126 0.073 0.034 0.011

U238 Energy deposition2) (calg fuel) 1.620 1.550 1.470 1.370

Energy deposition2) (J/g fuel) 6.780 6.490 6.150 5.730

Energy deposition3

) (per-unit) 1.000 0.957 0.907 0.846

Number of fissions xI10" 4 (fiss) 1.760 1.200 0.828 0.475

Power of fuel rod') (kW) 4.530 3.080 2.130 1.220

Pu239 Energy depositionO (caVg fuel) 58.20 66.00 91.00 156.0

Energy deposition2) (J/g fuel) 244.0 276.0 381.0 653.0

Energy deposition3) (per-unit) 0.373 0.423 0.583 1.000

Number of fissions x10" (fiss) 5.880 .4.200 3.040 1.830

Power of fuel rod') (kW) 1.490 1.060 0.767 0.463

Pu24' Energy deposition2 ) (caVg fuel) 19.10 ý22.70 32.90 59.50

Energy deposition2 ) (J/g fuel) 80.00 95.00 138.0 249.0

Energy deposition3) (per-unit) 0.321 0.382 0.553 1.000

Number of fissions x10"' (fiss) 2.120 1.350 0.801 0.381

Other Power of fuel rod') (kW) 0.005 0.003 0.002 0.001

isoto- Energy deposition?) (cal/g fuel) 0.069 0.073 0.087 0.124

pes Energy deposition2 ) (J/g fuel) 0.290 0.310 0.360 0.520

Energy deposition 3

) (per-unit) 0.558 0.590 0.702 1.000

Number of fissions x 10-14 (fiss) 3.980 2.580 1.600 0.812

Power of fuel rod') (kW) 10.10 6.540 4.060 2.060

Total Energy deposition2

) (cal/g fuel) 129.0 140.0 174.0 264.0

Energy deposition2

O (J/g fuel) 540.0 586.0 728.0 1105.

Energy deposition3) (per-unit) 0.489 0.530 0.659 1.000

1) at time of3.15 s, 2) at infinite time, 3) Current value per maximum value.

* All numerical values of characteristics were calculated for undamaged part of fuel stack only (See Table C.2.3.)

G-194
#B1OT ind~Pr t~~d~~~tlCs, ofi catedading Funel, R 6 7 Tes :

(Pr~irr~taa _ cieirradiated Claddinig) underIGR Tests

Table G-10.4. Fuel Enthalpy Vs. Time Calculated by FRAP-T6 Code for Fuel Rod #B1OT

Time Enthalpy at fuel radius Fuel e 1 Energy deposition

(cL/4 fuel) F in fueli trod

(S) 1.20 m 1 2-82 mm 13.47 mm 13.79 n cal/g fue Jig fuel cg fuel IJig fuel

'1

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

42

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

1.35

6.38

8.46

11.8

18.0

29.5

49.1

70.4

92.8

108

117

122

124

125

126

125

125

125

124

124

123

122

120

119

117

116

111

83.4

0.00

1.34

6.20

8.24

11.6

17.6

29.1

48.3

68.6

88.5

99.7

105

107

110

112

113

114

115

115

115

115

115

114

114

113

112

111

108

82.0

0.00

1.30

5.93

7.88

11.0

16.8

27.5

44.5

60.5

75.1

80.6

86.5

94.6

100

104

106

107

108

108

108

108

108

108

108

108

107

107

105

80.8

0.00

1.25

5.66

7.50

10.5

15.7

25.0

38.1

49.1

58.6

64.1

76.1

91.0

96.8

99.9

102

103

104

104

105

105

105

105

105

105

105

105

103

80.0

0.00

1.33

6.17

8.19

11.5

17.4

28.7

47.1

66.2,

85.1

95.8

103

108

112

114

115

115

116

116

116

116

115

115

114

113

,112

111

108

-82.0

0.00

5.58

25.8

34.3

48.1

73.1

120

197

277

356

402

431

453

468

476

481

483

485

485

485

484

483

482

477

474

470

466

452

344

0.00

1.50

7.02

9.24

12.7

19.0

30.6

50.0

70.7

92.3

107

116

121

125

128

130

131

132

133

134

134

135

135

136

137

137

138

140

143

0.00

6.28

29.4

38.7

53.4

79.5

128

209

296

387

.447

485

509

525

536

544

550

554

556

560

563

565

567

571

573

576

577

586

599 I I L .1 1

Radial enthalpy distribution and fuel enthalpy are presented at elevation 32.4 mm

Ma'dmum value of fuel enthalpy is 115.7 cal/g fuel (t=5.10 s)

1) All numerical values are presented at elevation with peak poer

G-195
I In~dividual Cli• • fRifabiicatcdFuel Rods' -I #B 10 T I tediafffted Cladding) under IY iTests

Table G-10.5. Energy Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for

Fuel Rod #B1OT

Time Energy Linear Fuel enthalpyt Leakage of energy') Clad-to-coolant heat

(im deposition') power') l l)L (al~g feel) transfer coefficient') (s) (eal/g fuel) (kW/m) (cal/g fuel) (cam/g fuel) 2K)

FAP-T6 S - SCT n W -T6 K)SCAN

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

1.59

7.46

9.83

13.6

20.2

32.5

53.2

75.2

98.1

113

123

129

133

136

138

140

141

141

142

143

143

144

145

146

146

147

148

152

0.00

5.90

17.8

262

43.8

81.1

148

-223

237

173

109

68.2

44.5

30.1

21.4

15.8

12.0

9.54

8.50

6.96

5.78

4.90

4.21

2.82

2.27

1.75

1.52

1.03

0.14

0.00

1.33

6.17

8.19

11.5

17.4

28.7

47.1

66.2

85.1

95.8

103

108

112

114

115

115

116

116

116

116

115

115

114

113

112

111

108

82.0

0.00

1.49

6.27

8.21

11.3

16.7

26.8

44.1

66.1

84.4

95.4

0.00

0.00

0.00

0.00

0.01

0.01

0.02

0.03

0.05

0.12

0.24

O.42

0.66

0.94

1.22

1.54

1.87

2.22

2.42

2.80

3.20

3.62

4.06

5.45

6.43

7.95

8.98

14.2

52.8

0.00

0.00

0.00

0.00

0.01

0.01

0.02

0.03

0.05

0.11

0.22

0.00

0.01

0.01

0.01

0.01

0.01

0.01

0.02

0.03

0.04

0.06

0.07

0.07

0.08

0.08

0.08

0.09

0.09

0.09

0.10

0.10

0.10

0.10

0.11

0.11

0.11

0.11

0.11

0.08

0.00

0.01

0.01

0.01

0.01

0.01

0.01

0.02

0.03

0.04

0.05

) All nmierical values are presented at elevation uith pcak powvr

G-196
M OT(PrRffdV M- iiiadite Cladding) unider IG'R Ts

Table G-10.6. Temperature Variation, Fission Gas Release and ZrO2 Thickness Vs. Time for Fuel

Rod t#B1DT Calculated by FRAP-T6 and SCANAIR Codes

Fuel centerline Fuel surface Clad outer Time JI Fission gas release

(s) temperature) temperature) temperature) (K) (K) ýK)

FRAP-T6 ISCANAIR FRAP-T6 ISCANAIR nRAPT6 ISCANAIR FRAP-T6 ISCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

317

399

432

483

573

736

1002

1281

1566

1750

1858

1916

1945

1957

1959

1957

1952

1949

1943

1936

1929

1921

1898

1883

1862

1848

1794

1448

293

317

393

423

468

547

687

918

1210

1460

1623

293

315

388

417

462

540

673

853

1001

1127

1200

1355

1543

1616

1654

1677

1691

1701

1705

1711

1714

1717

1719

1720

1720

1717

1713

1689

1405

293

316

387

415

459

533

665

866

1088

1248

1342

293

301

343

359

382

418

485

610

778

988

1131

1253

1285

1306

1331

1356

1380

1403

1414

1433

1451

1466

1480

1511

1525

1537

1542

1540

1306

293

301

342

357

379

413

474

584

752

945

1105

0.00

0.02

0.06

0.07

0.10

0.16

0.28

0.58

1.41

2.30

2.93

3.52

3.80

3.95

4.05

5.40

6.50

7.15

7.17

7.20

7.32

7.55

7.83

8.74

9.45

10.8

11.5

12.3

12.9

0.00

0.19

0.64

0.79

0.97

1.24

1.59

2.13

2.66

3.06

3.29

') All nmu-erical values are presented at elevation mith peak posw

G-197
#BLOT I(neividuat Claddingefabricated Fuel iRods I -Prir iaed~~zr~a~aed Claddng)i!under GRiTetsý -

Table G-10.7. Mechanical Characteristics of Fuel Rod #B1OT Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes

Clad outer Fuel hoop Fuel - clad gap Clad hoop Clad hoop Internal gas Time temperature') strain') width') straini) stressi) pressure

(s) (K) N (mm) (Y_) (MPa) (MPa)

FRAP.T6 SCAN FRAP.T6 SCANAIR FRAP-T6TSCANAIR FRAP-T6 SCANAIR FRAP-T6 SCAN'AIRFRAP.T6 SCANAIR

0.0

1.0

2.0

22

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

301

343

359

382

418

485

610

778

.988

1131

1253

1285

1306

1331

1356

1380

1403

1414

1433

1451

1466

1480

1511

1525

1537

1542

1540

1306

293

301

342

357

379

413

474

584

752

945

1105

0.00

0.06

0.18

0.23

0.30

0.43

0.68

1.11

1.64

2.17

2.50

2.75

2.90

2.99

3.05

3.13

3.23

3.31

3.33

3.29

3.19

3.31

3.40

3.73

4.02

4.10

4.10

3.92

2.51

0.00

0.02

0.07

0.09

0.13

0.19

0.32

0.54

0.85

1.14

1.34

0.06

0.06

0.06

0.05

0.05

0.05

0.04

0.03

0.01

0.00

0.00

0.02

2.15

2.15

2.15

2.15

2.14

2.14

2.14

2.14

2.14

2.14

2.14

2.12

2.11

2.11

2.11

2.12

2.17

0.07

0.07

0.07

0.07

0.07

0.07

0.06

0.06

0.05

0.05

0.04

0.01

0.01

0.04

0.05

0.07

0.09

0.14

0.23

0.35

0.55

0.82

1.44

54.7

54.7

54.8

54.8

54.8

54.8

54.8

54.9

54.9

54.9

54.9

54.9

54.9

55.0

55.0

55.0

54.7

0.01

0.01

0.05

0.06

0.07

0.10

0.15

0.24

0.37

0.51

0.60

8.72

8.83

9.12

9.21

9.34

9.52

9.76

10.0

10.3

65.1

26.9

11.0

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

8.70

8.84

9.17

9.28

9.43

9.64

9.94

10.3

10.6

10.7

10.4

1.70

1.70

1.75

1.77

1.79

1.83

1.87

1.92

1.96

2.00

2.02

2.04

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

1.70

1.72

1.78

1.80

1.82

1.85

1.90

1.94

1.98

2.01

2.02

') All numcrical values are presented at lcvation %ith peak powvr

G-198
#B10T I of RcfabrittedFue'l Rods -- ý

I: ( iidi~~!~j rradiated Clidding) niidirGR Tests;

Table G-10.8. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #B10T

Axial interval Energy deposition at infinite time Fuel enthalpy

from-to Energy depositio atifnietm at time (t=5.10 s)

(mm)-(mm) cal/g fuel J/g fuel per-unit cal/g fuel J/g fuel per-unit

25.0-39.8 155 649 1.00 116 485 1.00

39.8-54.6 146 610 0.94 109 455 0.94

54.6 - 69.4 149 624 0.96 111 466 0.96

69.4-84.2 148 619 0.95 110 462 0.95

84.2-99.0 146 610 0.94 109 456 0.94

99.0-113.8 144 605 0.93 108 452 0.93

113.8- 128.6 145 606 0.93 108 452 0.93

128.6- 143.4 144 601 0.93 107 449 0.93

143.4- 158.2 142 595 0.92 106 444 0.92

158.2- 173.0 140 586 0.90 104 438 0.90

4)

4)

4)

4)

I.-

0

0

4)

4)

160

140

____K _

100 -

80O

60--

40-

20" Energy depositio- Fuel enthalp

01

v

20" 40 60 80 100 120

Axial coordinate (mam)

140 160 180

Fig. G-10.5. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6 Code

for Fuel Rod #B10T

G-199
i lndividial C era &- efabricatid FuelRodsM OTe rditelF e irmdiaed Cladding) under IGRTet

1.2-[•U~

a 1.0

0.8

0.6

0.4

0.2

1 2 3 4

Radial fuel coordinate (mm)

1.2-

pun9

E 1.0-

C, ;

0.8-

0.6-

0.4

0.2

12 3 4

Radial fuel coordinate (mum)

Fig. G-10.6. U23 and Pu239 Radial Distributions of Energy Deposition for Fuel Rod #B1OT

G-200
#B1OT I lndiy siic of Refabricated Fuel Rods6"'). ,

, ( areirradajted Cladding) under IOR Tests

1.2 -I. *I.

0

1.0

0.8

0.6

.4- +

.4- t t

0.4 1

3

3

0.2 -

1 2 4

Radial fuel coordinate (mm)

140

4)

4.-

eli

C.

C

1.0 1.5 2.0 2.5 3.0 3.5 4.0

Radial fuel coordinate (mm)

Fig. G-10.7. Radial Distributions of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #BIOT

G-201
#B1OT :iidtvduaq (IP (-hrac ofiijusp~f b 6abi4Oatered dtgdiIRod Fue ist (Prerradate _Tiiý,ted Claddig ne G et

250

200

150

10100

50'

0

2000

1600

,.•1200

E goo

4O0

0

150

120

90

60

30

0

30

0.1

0 1 2 3 4 5 6 7 8 9 10

Time (s)

0.1ZU

0

U0.09

O.06

O.03- 0

0.03-5

f4

2

0.00

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. G-10.8. Energy and Temperature Characteristics Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes for Fuel Rod #B1OT

G-202
#B1OT I ~ of Refabricatcd Fuel Rods~

2.5

2.0

2 1.5

I.

E

0.5

0.0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

100

80

60

L.,

0 0 40

25-

2000

3.0

2.5

2.0 2

1.5~cc

LL.

0.5

0.0

a.

0

0

*0

C'S

0 1 2 3 4 5

Time (s)

7 8 9 10

Fig. G-10.9. Cladding Mechanical Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #B1OT

G-203
#B1OT ltPreifridiiated~nAýrq ed Cladding) under IGR Tests 5==:l

5.0

4.0

"• 3.0

LT.•2.0

1.0

0.0

2500

2000

1500

E

.2

1000

500

0

0 1 2. 3 4 5 6 7 8 9 10

Time (s)

14

12

.10

u.8

4

2

0

0 1 2 3 4 5

Time (s)

6 7 8 9 10

Fig. G-10.10. Fuel Strain and Fission Gas Release Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #B10T

G-204
'Jlndityt itstics of Refabricated Fue! Rods

#B lOT I d Cladding) ClaP-,rradlat•d underloR Tests -

Table G-10.9. Some Results of PIE for Fuel Rod #B1OT

Characteristic Value

1. Measured parameters of cladding oxidation and cladding

deformation

1.1. Cladding thickness at elevation 38, 98 mm correspondent to

different azimuthal angles (urn):

00 545 680

900 R 677

1800 580 649

2700 620 663

1.2. ZrO2 thickness at elevation 38, 98 mm correspondent to different

azimuthal angles (pin):

00 10 10"

900 - 10

1800 10 10

2700 10 10

1.3. ctZr(O) thickness at elevation 38, 98 mm correspondent to different

azimuthal angles (tun):

00 10 10

900 - 10

1800 10 10

2700. 10 10

1.4. Clad hoop strain at elevation 38, 98 mm, respectively (%) 33.4 3.7

2. Measured parameters for FGR analysis

2.1. Internal gas composition (% by volume):

He

N2

02

Ar

CO2

Kr

Xe

2.2. Free gas volume (cm3

)

2.3. Gas pressure inside fuel rod under normal condition (MPa)

2.4. Kr concentration in fuel (cm 3

/g fuel)

3. Measured parameters of cladding hydriding

3.1. Coefficient of hydride orientation (per-unit)

3.2. _ Hydrogen concentration (% by weight)

G-205
#B10T Indiv'iPrduAls n i R of• iated Fad fl )unde Rod s -

;(P'ririadiate4 I r~e~im"tc-d Cladding).undei' IGRjTests::

Table G-10.10. General Characteristic of Fuel Rod #B1OT

Parameter Unit Value

Experiment FRAP-T6 SCANAIR

1 Type of coolant - air air air

2 Burnup MWd/kg U 43.0 43.0 43.0

3 Energy deposition in fuel rod callg fuel 146 146 146

4 Peak fuel enthalpy cal/g fuel - 116 -

5 Peak fuel temperature K - 1959

6 Peak clad temperature. K - 1545

7 Fuel rod failure Yes, No Yes Yes

8 Type of failure:

- cladding rupture due to ballooning Yes, No Yes Yes

- cladding rupture due to PCMI Yes, No No No

- fragmentation of fuel rod Yes, No No -

9 Failure time s - 3.92 _

10 Fuel enthalpy at failure cal/g fuel - 106

11 Outer cladding temperature at failure K - 1279

12 Internal gas pressure at failure MPa - 2.02

13 ZrO2 thickness after test Pm 10 -

14 Residual clad hoop strain:

- peak value for ballooning area % 33.4 54.40

- other locationt) % 3.7 0.83

15 15composition Kr concentration after in test___________ internal gas % by volume - 1.20

16 Xe concentration in internal gas % by volume - 7.19

composition after test

17 Kr concentration in fuel after test cm3

/g fuel - 0.11

"Calculated values by FRAP-T6 and SCANAIR codes are average along height of fuel rod excluding ballooning region

G-206
4 .

reteristicsfor 'F'We" l\?•: iT under!•:- ' .IGR..'i••, Tesi.:.i t,

G-207
#B11T 4Ytiradn ue, *r nrmaiaf&1 CladdinA, under IGRc Tst

Fig. G-11.1. Appearance of Fuel Rod #B11T (photographs and X-ray photograph)

G-208
#B11T hliv~f ha itciý,tcý d o lýflý) :,tc ud Ro S

ýPrcirmdiated Fu-PeraitdCadn ~ ~ ~ r (&Re

Fig. G-11.2. Cross-Section and Cladding Microstructure for Fragment of Fuel Rod #B11T

G-209
MI1T I i u id~ ýi C I ýIcrtis s otRotfa Iicat,ýd IF IefýI R ("

cirreitiiaa,: FmdePc rtdiic1 Cldad d i n-)underi16 I !:tes

I

Fig. G-11.3. Fuel Microstructure for Fragment of Fuel Rod #B11T at 50 mm Elevation

G-210
#B11T I Gd~ivdaii~harctristics of Refabriic'ated Fuiel Ro s'>;. I ~ Cadding j irdei IGk Tsts W: I

Table G-11.1. Time Dependent Energy Characteristics of Fuel Rod #BllT

Reac- Cumulative number of fissions Power Energy

tor in fuel rod (fiss) of fuel deposition

Time energy rod in fuel rod

(s) deposi- U23 pu23 9 Pu 24 ' Other Total (k) cal/g J/g fuel

X10n) l xlO"1 xlOq1 4 x10 14 iso- x10' 4 fuel

(%) ftopes xl0-"

0.0

1.0

2.0

2.2

2.4

2.6

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

9.0

10.0

20.0

30.0

0O

0.000

0.734

4.900

6.890

9.680

13.70

19.80

29.40

44.70

62.70

74.80

81.90

86.00

88.60

90.30

91.50

92.40

93.10

93.70

94.10

94.50

94.80

95.00

95.60

95.90

96.20

96.50

96.90

97.20

98.60

99.10

100.0

0.000

0.058

0.385

0.540

0.760

1.080

1.550

2.310

3.510

4.920

5.870

6.420

6.750

6.950

7.090

7.180

7.250

7.310

7.350

7.390

7.410

7.440

7.460

7.500

7.530

7.550

7.570

7.600

7.630

7.740

7.780

7.850

0.000

0.019

0.125

0.175

0.246

0.349

0.503

0.747

1.140

1.590

1.900

2.080

2.190

2.250

2.300

2.330

2.350

2.370

2.380

2.390

2.400

2.410

2.420

2.430

2.440

2.450

2.450

2.460

2.470

2.510

2.520

2.540

0.000

0.082

0.547

0.768

1.080

1.530

2.210

3.280

4.980

6.990

8.350

9.130

9.590

9.880

10.10

10.20

10.30

10.40

10.40

10.50

10.50

10.60

10.60

10.70

10.70

10.70

10.80

10.80

10.80

11.00

11.00

11.20

0.000

0.029

0.194

0.272

0.383

0.542

0.782

1.160

1.770

2.480

2.960

3.240

3.400

3.500

3.570

3.620

3.650

3.680

3.700

3.720

3.730

3.750

3.760

3.780

3.790

3.800

3.810

3.830

3.840

3.900

3.920

3.950

0.000

0.092

0.613

0.861

1.210

1.710

2.470

3.670

5.590

7.830

9.360

10.20

10.70

11.10

11.30

11.40

11.60

11.60

11.70

11.80

11.80

11.80

11.90

11.90

12.00

12.00

12.10

12.10

12.20

12.30

12.40

12.50

0.000

0.171

1.140

1.600

2.250

3.180

4.590

6.820

10.40

14.50

17.40

19.00

20.00

20.60

21.00

21.20

21.50

21.60

21.70

21.90

21.90

22.00

22.10

22.20

22.30

22.30

22.40

22.50

22.60

22.90

23.00

23.20

0.000

1.090

5.570

7.770

11.00

16.20

24.90

40.20

61.40

51.80

30.60

17.70

10.80

7.070

4.920

3.600

2.750

2.180

1.780

1.450

1.240

1.060

0.923

0.677

0.527

0.432

0.367

0.316

0.254

0.066

0.035

0.000

0.000

2.020

13.50

19.00

26.70

37.80

54.50

80.90

123.0

173.0

206.0

226.0

237.0

244.0

249.0

253.0

255.0

257.0

259.0

260.0

262.0

262.0

263.0

265.0

266.0

267.0

268.0

269.0

271.0

276.0

278.0

284.0

0.000

8.460

56.50

79.50

112.0

158.0

228.0

339.0

515.0

724.0

862.0

946.0

992.0

1021.

1042.

1059.

1067.

1076.

1084.

1088.

1097.

1097.

1101.

1109.

1113.

1118.

1122.

1126.

1134.

1155.

1164.

1189. L £ .5 .5. & .5. 5. 5

Maximum value of power is 63.6 kW (t = 3.25 s).

I) Current energy deposition per maximum energy deposition (at infinite time)

G-21 1
#B11T Indi vrIrdual 6T las.edCladdicatngerhed st tFueflR 

(Priir adiat 'jiHfi~d aiddirig)iunder IGRTests

Table G-11.2. Axial Energy Characteristics of Fuel Rod #B11T

Axial Cumulative number of fissions Maxi- Energy deposition

coordi- at axial interval (fiss) mum at infinite time*

nate U u3 p3 p4

from U23 U23 PuP9 Pu24 Other Total power of cal/g J/g perlower xIO- 3 xlO-" xIO"13 xIO1 3 iso- xlO" 3 lower I I ~~~(kW) fuel rod fuele fuell unie)i3

end of topes t=3.25s

fuel rod x1010

(mm)

10.0

15.0

20.0')

25.0

30.0

35.0

40.0

45.0

50.0

55.0

60.0

65.0

70.0

75.0

80.0

85.0

'90.0

95.0

100.0

105.0

110.0

115.0

120.0

125.0

130.0

135.0

140.0

145.0

150.0

155.0

160.0

165.0

170.0

175.0

180.02)

185.0

0.000

0.000

1.400

1.750

2.840

2.680

2.800

2.810

2.650

2.730

2.730

2.670

2.490

2.700

2.750

2.800

2.840

2.870

2.900

2.880

2.850

2.790

2.670

2.050

2.050

2.050

2.050

2.040

2.040

2.040

2.040

2.040

2.040

2.040

0.407

0.000

0.000.

0.000

4.020

5.030

8.960

8.690

9.280

9.450

8.990

9.280

9.280

9.030

8.370

9.000

9.100

9.180

9.230

9.290

9.350

9.310

9.210

9.120

8.870

6.480

6.480

6.480

6.480

6.570

6.570

6.570

6.570

6.320

6.320

6.320

1.260

0.000

0.000

0.000

1.890

2.370

4.030

3.810

4.000

4.020

3.800

3.910

3.910

3.820

3.560

3.860

3.940

3.990

4.040

4.080

4.120

4.100

4.030

3.950

3.770

2.910

0.000

0.000

0.662

0.828

1.430

1.350

1.420

1.420

1.340

1.380

1.380

1.350

1.250

1.360

1.390

1.410

1.430

1.440

1.460

1.450

1.430

1.400

1.330

1.040

1.040

1.040

1.040

1.030

1.030

1.030

1.030

1.050

1.050

1.050

0.209

0.000

0.000

0.000

1.910

2.390

4.470

4.470

4.480

4.490

4.490

4.490

4.490

4.490

4.500

4.500

4.500

4.500

4.500

4.510

4.510

4.520

4.530

4.540

4.550

3.200

3.200

3.200

3.200

3.110

3.110

3.110

3.110

3.110

3.110

3.110

0.621

0.000

0.000

0.000

4.000

4.990

8.400

7.940

8.310

8.350

7.880

8.120

8.120

7.940

7.390

8.010

8.170

8.300

8.400

8.500

8.570

8.520

8.400

8.230

7.870

6.080

6.080

6.080

6.080

5.980

5.980

5.980

5.980

6.120

6.120

6.120

1.220

0.000

0.000

0.000

1.090

1.370

2.300

2.170

2.280

2.290

2.160

2.220

2.220

2.170

2.020

2.190

2.240

2.270

2.300

2.330

2.350

2.330

2.300

2.250

2.150

1.660

1.660

0.000

0.000

306.0

306.0

296.0

291.0

287.0

284.0

282.0

281.0

281.0

282.0

283.0

284.0

285.0

286.0

287.0

287.0

287.0

286.0

285.0

282.0

277.0

279.0

279.0

279.0

279.0

275.0

275.0

275.0

275.0

281.0

281.0

281.0

281.0

0.000

0.000

0.000

1281.

1281.

1239.

1218.

1201.

1189.

1180.

1176.

1176.

1180.

1185.

1189.

1193.

1197.

1201.

1201.

1201.

1197.

1193.

1180.

1160.

1168.

1168.

1168.

1168.

1151.

1151.

1151.

1151.

1176.

1176.

1176.

1176.

0.000

0.00

0.00

1.00

1.00

0.97

0.95

0.94

0.93

0.92

0.92

0.92

0.92

0.92

0.93

0.93

0.93

0.94

0.94

0.94

0.93

0.93

0.92

0.91

0.91

0.91

0.91

0.91

0.90

0.90

0.90

0.90

0.92

0.92

0.92

0.92

0.00

2.910

2.910

2.910

2.840

2.840

2.840

2.840

2.970

2.970

2.970

0.593

0.000

1.660

1.660

1.640

1.640

1.640

1.640

1.670

1.670

1.670

"0.335

0.000

All numerical values ofcharacteristics are presented as average values at the length interval equal to the axial coordinate :t 2.5 mm

I) Initial coordinate of fuel is 18.5 nmm

2) End coordinate of fuel is 178.5 mm

3) Current value per maximum value.

G-212
#B11T ; iitis d tf Cladding) un!e Rodst' iii

Table G-11.3. Radial Energy Characteristics of Fuel Rod #BI1T

Coordinates of fuel zones (mm)

Characteristics* I zone 2 zone 3 zone 4 zone

1.2-2.811 2.811-3.432 3.432-3.704 3.704-3.790

Number of fissions xI-0" 4 (fiss) 2.660 1.570 0.771 0.252

Power of fuel rod') (kW) 7.150 4.210 2.070 0.676

U235 Energy deposition2) (caLg fuel) 95.70 94.00 92.50 90.50

Energy deposition 2

) (Jig fuel) 401.0 393.0 387.0 379.0

Energy deposition 3

) (per-unit) 1.000 0.982 0.967 0.946

Number of fissions X 10-12 (fiss) 8.940 5.150 2.440 0.757

Power of fuel rod') (kW) 0.237 0.137 0.065 0.020

U23

8 Energy deposition 2

) (cal/g fuel) 3.180 3.050 2.900 2.690

Energy deposition 2

) (J/g fuel) 13.30 12.80 12.10 11.30

Energy deposition3) (per-unit) 1.000 0.959 0.912 0.846

Number of fissions X10"14 (fiss) 3.090 2.110 1.450 0.830

Power of fuel rod') (kW) 8.580 5.840 4.030 2.300

Pu239 Energy deposition2 ) (cal/g fuel) 115.0 130.0 180.0 309.0

Energy deposition2 ) (J/g fuel) 481.0 544:0 753.0 1293.

Energy deposition3) (per-unit) 0.372 0.421 0.583 1.000

Number of fissions x 10"13 (fiss) 10.40 7.420 5.360 3.230

Power of fuel rod') (kW) 2.840 2.030 1.460 0.882

Pu241 Energy deposition2 ) (callg fuel) 38.10 45.30 65.50 118.0

Energy deposition2 ) (J/g fuel) 159.0 190.0 274.0 494.0

Energy deposition 3

) (per-unit) 0.323 0.384 0.555 1.000

Number of fissions x10-" (fiss) 3.900 2.480 1.480 0.701

Other Power of fuel rod') (kW) 0.011 0.007 0.004 0.002

isoto- Energy deposition2 ) (caVg fuel) 0.144 0.152 0.181 0.258

pes Energy deposition2 ) (J/g fuel) 0.600 0.640 0.760 1.080

Energy deposition3) (per-unit) 0.558 0.589 0.702 1.000

Number of fissions x10"-4 (fiss) 6.880 4.460 2.780 1.410

Power offuel rod' (kW) 18.80 12.20 7.610 3.860

Total Energy deposition2) (cal/g fuel) 253.0 273.0 340.0 517.0

Energy deposition2 ) (J/g fuel) 1059. 1143. 1423. 2164.

1 Energy deposition3) (per-unit) 0.489 0.528 0.658 1.000

1) at time of 3.25 s. 2) at infinite time, 3) Current value per maximum value.'

0 All numerical values of characteristics were calculated for undamaged part offuel stack only (See Table C.2.3.)

G-213
#B11T I f(Preirradiatc z•i]•ated Cladding) under IGR Tests

Table G-11.4. Fuel Enthalpy Vs. Time Calculated by FRAP-T6 Code for Fuel Rod #B111T

Time Enthalpy at fuel radius Fuel thal Energy deposition

Time fuel) 1(alI/4 Fuel in fuel rod 1.20 mm 2.82 mm 3.47 mm 3.79 mm calg fuel J/g fuel cal/g fuel I J/g fuel

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

2.06

15.3

20.8

28.5

39.7

57.0

84.9

130

181

221

245

258

265

268

269

269

267

0.00

2.03

14.9

20.1

27.5

38.4

55.0

81.9

125

174

209

229

237

240

240

240

238

237

0.00

1.95

13.9

18.7

25.3

35.0

49.3

71.6

106

146

177

190

195

198

200

202

202

201

0.00

1.85

12.8

17.1

22.9

30.8

41.7

57.5

76.6

122

144

154

163

171

176

179

180

180

0.00

2.01

14.6

19.7

26.9

37.4

53.2

78.3

118

165

200

218

227

232

234

235

234

233

0.00

8.42

61.3

82.6

113

156

223

328

494

692

838

914.

952

972

981

983

980

975

0.00

2.25

16.0

21.5

292

40.4

57.4

84.4

126

172

205

225

236

244

248

252

254

256

258

259

260

261

262

264

265

266

267

271

278

0.00

9.44

66.9

89.9

122

169

241

354

529

722

861

942

991

1021

1041

1056

1066

1075

1081

1087

1091

1095

1099

1106

1111

1115

1118

1133

1165

Radial enh If distnbution and fuel enthalpy are presented at elevation 26.5 mm

Maximum value of fuel enthalpy is 234.5 cal/g fuel (t--4.61 s)

1 All numerical values ae presented at elevation %ith peak poer

G-214
#B11T Csof Refabricated Fuel Rods

AM ,ýPt iiraiitei Clding'ne O

Table G-11.5. Energy Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for

Fuel Rod #B11T

Time depTsitine) Energy power Linear 1) Fuel fuel) en1apy) Leakage Leakag of fuel) enerJy Clad-to-coolant transfer coefficienti) heat

(s) (alful (k/) (cal/g fuel) (cal/g fuel)2

() (cal/g fuel) (kW/m) (/mK)

FRAP-T6 ISCANAIR nRA-T6 SCNI scRAR -T6 ISCANAiR

0.0

1.0

2.0

22

2.4

2.6

2.8

3.0

3.2

3A

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

2.39

16.9

22.8

31.0

42.9

60.9

89.5

134

183

218

239

251

258

264

267

270

272

274

275

276

277

278

280

281

282

283

286

295

0.00

8.73

44.1

61.5

87.2

129

198

319

478

401

237

137

83.7

54.8

38.2

28.0

21.4

17.0

14.1

11.5

9.69

828

7.29

5.28

4.14

3.38

2.87

1.99

0.27

0.00

2.01

14.6

19.7

26.9

37.4

53.2

78.3

118

165

200

218

227

232

234

235

234

233

0.00

1.49

627

821

11.3

16.7

26.8

44.1

66.1

84.4

95.4

0.00

0.00

0.01

0.01

0.02

0.03

0.05

0.09

0.18

0.38

0.72

1.34

2.26

3.45

4.85

6.37

7.89

9.41

0.00

0.00

0.00

0.00

0.01

0.01

0.02

0.03

0.05

0.11

0.22

0.00

0.01

0.01

0.01

0.01

0.02

0.02

0.03

0.05

0.08

0.11

0.16

0.20

0.23

0.25

0.25

0.25

0.25

0.00

0.01

0.01

0.01

0.01

0.01

0.01

0.02

0.03

0.04

0.05

) All nmercal valucs arc p•-csnted at ccvation with peak po•wr

G-215
IndividtWal Ch ___t_- _ 'of Refabricated Fuel Rods #B11T (Preirradiated Fu rdiated Cladding) under IGR Tcsts

Table G-11.6. Temperature Variation, Fission Gas Release and ZrO2 Thickness Vs. Time for Fuel

Rod #B11T Calculated by FRAP-T6 and SCANAIR Codes

Time Fuel centerline Fuel surface Clad outer i Time tep Ie ~e ep) Fission gas release temperaturet temperaturel) temperaturel)()

(s) (K) (K) (K) I (Y)

_ FRAP-T6 SCANAIR FRAP-T6 ISCANAIR FRAP-T6 [SCANAIR FRAP-T6 SCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

329

534

613

721

876

1106

1466

2004

2512

2815

2969

3047

3086

3105

3110

3107

3098

293

317

393

423

468

547

687

918

1210

1460

1623

293

325

498

560

643

754

902

1113

1361

1922

2157

2265

2347

2420

2468

2492

2503

2500

293

316

387

415

459

533

665

866

1088

1248

1342

293

303

390

431

487

566

685

871

1103

1298

i536

1753

1909

2012

2085

2092

2092

2094

293

301

342

357

379

413

474

584

752

945

1105

0.00

0.10

0.51

0.73

1.06

1.59

2.45

4.14

6.49

9.97

22.1

40.7

57.1

69.9

78.6

83.3

85.4

86.3

0.00

0.19

0.64

0.79

0.97

1.24

1.59

2.13

2.66

3.06

3.29

__________________ 1 1. a n a. J.

G-216

J
#B11T I Individual aradteristics of Refabricated Fuel Rods

(Preirraidi; 'det., Preirradiated Cladding) under IGR Tests

Table G-11.7. Mechanical Characteristics of Fuel Rod #B11T Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes

Clad outer Fuel hoop Fuel - clad gap Clad hoop Clad hoop Internal gas Time temperature' strain 1) width') strain1 stress" pressure

(K) (%) (mm) M%) (MPa) (MPa)

RA-T6 S ANAI RP-T61 SCANAIR FRAP-T6 SCNAIR FRAP-T61SCANAIM FRAP-T6jSCANAI. FRAP-T6 SCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

303

390

431

487

566

685

871

1103

1298

1536

1753

1909

2012

2085

2092

2092

2094

293

301

342

357

379

413

474

584

752

945

1105

0.00

0.12

0.49

0.63

0.82

1.10

1.52

2.20

3.14

4.41

6.17

6.95

7.02

6.78

6.77

6.46

6.44

6.34

0.00

0.02

0.07

0.09

0.13

0.19

0.32

0.54

0.85

1.14

1.34

0.07

0.07

0.05

0.05

0.04

0.04

0.02

0.00

0.00

1.57

1.50

1.47

1.47

1.48

1.48

1.49

1.49

1.49

0.07 1 0.01 1 0.01

0.07

0.07

0.07

0.07

0.07

0.06

0.06

0.05

0.05

0.04

0.02

0.08

0.10

0.14

0.20

0.28

0.41

1.17

42.6

42.8

43.0

43.1

43.2

43.3

43.3

43.3

43.3

0.01

0.05

0.06

0.07

0.10

0.15

0.24

0.37

0.51

0.60

8.88

9.07

9.75

9.92

10.1

10.4

10.6

11.0

20.6

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

8.70

8.84

9.17

9.28

9.43

9.64

9.94

10.3

10.6

10.7

10.4

1.70

1.73

1.85

1.88

1.91

1.96

2.01

2.08

2.15

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10.

1.70

1.72

1.78

1.80

1.82

1.85

1.90

1.94

1.98

2.01

2.02

J. J. _________ L I I I I................L .L

I) All numerical values are presented at elevation ,iith peak poiwvr

G-217
#B11T 'lndividua CharaidrMigofRefabricated Fuel Rods

(Preirradiated Fuajf__irdiated Cladding)'under IGR Tests

Table G-11.8. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #B1T

Axial interval E Fuel enthalpy

from-to nergy deposition at infinite time at time (t=4.61 s)

(mm)-(mm) caVg fuel J/g fuel per-unit cal/g fuel J/g fuel per-unit

18.5-34.5 301 1261 1.00 235 983 1.00

34.5 - 50.5 286 1198 0.95 223 933 0.95

50.5-66.5 281 1179 0.93 219 919 0.93

66.5-82.5 284 1190 0.94 221 927 0.94

82.5 -98.5 287 1201 0.95 .223 936 0.95

98.5-114.5 285 1196 0.95 222 932 0.95

114.5 - 130.5 279 1169 0.93 217 911 0.93

130.5 - 146.5 278 1165 0.92 217 908 0.92

146.5 - 162.5 275 1153 0.91 214 899 0.91

162.5 - 178.5 281 1176 0.93 219 917 0.93

350

S300

'ý 250

VS:

200

• 150

.2

100

4)

q 50

0

0 30 60 90 120 150

Axial coordinate (mm)

IgO

Fig. G-11.4. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6 Code

for Fuel Rod #B11T

G-2 18
#B11T IndivlJ• Sai eristics of Rcfabricted Ruel Rods

(Preirr6diýrI p Preirradiated Cladding) hnider IGR Tests

1.2

J4N

0

C,

w

1.0

0.8

0.6

0.4

2

U235

0.2

1.2

i

3 4

Radial fuel coordinate (mm)

.E! C)

C

0

1.0

0.8

0.6

0.4

0.2

1 2 3 4

Radial fuel coordinate (mum)

Fig. G-11.5. U" and Pu239 Radial Distributions of Energy Deposition for Fuel Rod #B11T

G-219
#B11T Individual 'e67ofRefabricated Fuel Rods

I,(Preirradiated Fu170ediatd Cladding) under IGR Tests-.;

1.2

I

0

0~

1.0

0.8

0.6

0A

02- I i !

I 2 3 4

Radial fuel coordinate (mm)

300

0

£1

0

C3

1.0 1.5 2.0 2.5 3.0 3.5 4.0

Radial fuel coordinate (mm)

Fig. G-11.6. Radial Distributions of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #Bl1T

G-220
#B11T I lndividual.•''iaracterscs of Refabricated Fuel Rods

I (lreirrad i'el, Preirrndiated Cladding) under IGR Tests

500

400

300

>- 200

100

300

240

CI

180 '-

120

60

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

3500 . tFRAP-T6

.... SCANAIR

3000 *- Fuel centerline temperature

- Clad outer temperature

-- CF- Heat transfer coefficient

2500 I '----

c 2000-

0 E1500-

1000 -

500- - -

0T

0.35

0.30_

0-.20

0.205

0.10

U

0 u

0.05~

0.00

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. G-11.7. Energy and Temperature Characteristics Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes forFuel Rod #B11T

G-221
#B11T Individual ChaiaideiTiofRefabricated Fuel Rods':,..

(Preirradiat ltiated d Fu q" Cladding) Under IGR Tests

2.

2.

E

0.

0.

5

4

0

0

2

.5

.0

.5

- FRAP-T6

S-.--- SCANAIR

. Internal gas pressure

.3 Clad hoop stress

.U

0 1 2 3 4 5 6 7 8 9 10

Time (s)

0-

0-

0- -SANI

0-" FRAN-T6"- .... SCANAIR

- - Clad hoop strain

-- Fuel-clad gap width

oA -"

50

40

30 -.

20

10

0

2.0

1.6

EE

1.2 -S

0.8 V

Y

0.4

0.0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. G-11.8. Cladding Mechanical Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #B1lT

G-222
#B11T Indidual p-iiaratenstics of Refabricated Fuel Rods

SPreradiated Cladding) under IGR Tests

10

8

6

C0

0

3500

2800

2100 3

E

1400

700

0

4

2

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

100

80

60

.E

>1

40

20

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. G-11.9. Fuel Strain and Fission Gas Release Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #BIlT

G-223
MI1T Individual Chracte•t-r fcoRefabricated Fuel Rods,`-

(Preirradiited Fueli. -diated Cladding) under IGR Tests : :

Table G-11.9. General Characteristic of Fuel Rod MBlIT

Parameter Unit Value

Experiment FRAP-T6 SCANAIR

I Type of coolant -- air air air

2 Burnup MWd/kg U 43.6 43.6 43.6

3 Energy deposition in fuel rod cal/g fuel 284 284 284

4 Peak fuel enthalpy cal/g fuel - -

5 Peak fuel temperature K - -

6 Peak clad temperature K -

7 Fuel rod failure Yes, No Yes Yes -

8 Type of failure:

- cladding rupture due to ballooning Yes, No ? Yes

- cladding rupture due to PCMI Yes, No ? No

- fragmentation of fuel rod Yes, No Yes -

9 Failure time s - 3.31

10 Fuel enthalpy at failure cal/g fuel - 141

11 Outer cladding temperature at failure K - 1211

12 Internal gas pressure at failure MPa - 2.20

13 ZrO2 thickness after test Pim - -

14 Residual clad hoop strain:

- peak value for ballooning area %- -

- other locationi) - -

15 Kr concentration in internal gas % by volume - - composition after test

Xe concentration in internal gas % by volume 16 composition after test

17 Kr concentration in fuel after test cm 3

/g fuel -

"Calculated values by FRAP-T6 and SCANAIR codes arc average along height of fuel rod excluding ballooning region

G-224
G-225
IndPr~ivirdin ____ Redfabricatdd FuelIdP ',1 #B12T I diat (Pren irm~edCladdin'g) unerIG Test-]-

Positionif- (90P)

F7

!

Fig. G-12.1. Appearance of Fuel Rod #B12T (photographs and X-ray photograph)

G-226
#B12T

w 11

Position 1

Position 2

Fig. G-12.2. Cross-Section and Cladding Microstructure for Fuel Rod #B12T at 85 mm Elevation

G-227
#B12T

Pn~itinn 1

Fig. G-12.3. Cross-Section and Cladding Microstructure for Fuel Rod #B12T at 140 mm Elevation

G-228
#B12T i O~~~d ~ iimdi C~ding) Catd under- IOR ,Tests-.-?

Fig. G-12.4. Fuel Microstructure for Fuel Rod #B12T at 85 mm Elevation

G-229
#B12T I Jnit idu.,45-a ýrl~ C MLefabricated FuelRIls K-:

ff,(PeirridiWtdýi ý 44~1~d Claddingi indcrlIGRTests< I

Table G-12.1. Time Dependent Energy Characteristics of Fuel Rod #B12T

Reac- Cumulative number of fissions Power Energy

tor in fuel rod (fiss) of fuel deposition

Time energy rod in fuel rod

(s) deposi- U235 U38 Pu239 Pu24' Other Total (kW) cal/g J/g fuel

tion xI0-14 xl0"13 x0"14 xI0"14 iso- xI0"14 fuel

(%) Itopes x10-1I

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

9.0

10.0

20.0

30.0

Do

0.000

0.709

6.580

9.810

14.70

22.30

35.10

53.50

68.70

78.30

84.20

87.80

90.20

91.70

92.70

93.50

94.10

94.50

94.90

95.20

95.50

95.70

95.90

96.30

96.60

96.80

97.10

97.40

97.70

99.00

99.50

100.0

0.000

0.026

0.239

0.356

0.533

0.810

1.280

1.940

2.490

2.850

3.060

3.190

3.270

3.330

3.370

3.400

3.420

3.430

3.450

3.460

3.470

3.480

3.480

3.500

3.510

3.520

3.530

3.540

3.550

3.600

3.610

3.650

0.000

0.011

0.102

0.152

0.227

0.346

0.544

0.829

1.060

1.210

1.310

1.360

1.400

1.420

1.440

1.450

1.460

1.460

1.470

1.470

1.480

1.480

.1.490

1.490

1.500

1.500

1.500

1.510

1.510

1.530

1.540

1.560

0.000

0.045

0.414

0.618

0.924

1.400

2.210

3.370

4.320

4.930

5.300

5.530

5.680

5.770

5.840

5.890

5.920

5.950

5.970

5.990

6.010

6.020

6.040

6.060

6.080

6.100

6.110

6.130

6.150

6.240

6.260

6.320

0.000

0.017

0.161

0.240

0.359

0.546

0.860

1.310

1.680

1.920

2.060

2.150

2.210

2.240

2.270

2.290

2.300

2.310

2.320

2.330

2.340

2.340

2.350

2.360

2.360

2.370

2.380

2.380

2.390

2.420

2.440

2.460

0.000 0.000

0.056

0.522

0.779

1.160

1.770

2.790

4.250

5.450

6.220

6.690

6.980

7.160

7.280

7.360

7.430

7.470

7.500

7.530,

7.560

7.580

7.600

7.610

7.650

7.670

7.690

7.710

7.740

7.760•,

7.870

7.900

7.970

0.089

0.825

1.230

1.840

2.800

4.400

6.710

8.610

9.820

10.60

11.00

11.30

11.50

11.60

11.70

11.80

11.80

11.90

11.90

12.00

12.00

12.00

12.10

12.10

12.10

12.20

12.20

12.30

12.40

12.50

12.60

0.000

0.615

4.770

7.040

10.70

17.40

29.60

32.20

22.00

13.50

8.250

5.200

3.420

2.350

1.680

1.250

0.956

0.792

0.674

0.580

0.503

0.441

0.391

0.301

0.244

0.206

0.180

0.157

0.128

0.000

1.270

11.80

17.60

26.30

40.10

63.10

96.00

123.0

141.0

151.0

158.0

162.0

165.0

167.0

168.0

170.0

170.0

171.0

172.0

172.0

173.0

173.0

174.0

175.0

175.0

176.0

177.0

177.0

181.0

182.0

186.0

0.000

5.320

49.40

73.70

110.0

168.0

264.0

402.0

515.0

590.0

632.0

661.0

678.0

691.0

699.0

703.0

712.0

712.0

716.0

720.0

720.0

724.0

724.0

728.0

733.0

733.0

737.0

741.0

741.0

758.0

762.0

779.0

0.035

0.019

0.000

Maximum value of power is 34.5 kW (t - 2.90 s).

1) Current energy deposition per maximum energy deposition (at infinite time)

G-230
#B12T 1,( _ di iradiatd Cladding) underIG'RTests;,,-

Table G-12.2. Axial Energy Characteristics of Fuel Rod #B12T

Axial Cumulative number of fissions Maxi- Energy deposition

coordi- at axial interval (fiss) mum at infinite time*

nate u235 u238 pu p4of

from Pu" 9 Pu 4 ' Other Total power callg J/g perlower XIO"1 X -" 10"13 x]101 3 iso- X10.13 fuel rod fuel fuel unit3 )

end of topes (W)

fuel rod x10 "1 0

(mm) _ _ _ I I

10.01)

15.0

20.0

25.0

30.0

35.0

40.0

45.0

50.0

55.0

60.0

65.0

70.0

75.0

80.0

85.0

90.0

95.0

100.0

105.0

110.0

115.0

120.0

125.0

130.0

135.0

140.0

145.0

150.0

155.0

160.0

165.0

170.02)

175.0

180.0

185.0

0.444

1.110

1.110

1.080

1.080

1.080

1.080

1.080

1.040

1.040

1.040

1.050

1.050

1.050

1.050

1.050

1.050

1.050

1.010

1.010

1.010

1.570

1.570

1.560

1.620

1.680

0.987

0.987

0.987

0.982

0.982

0.982

0.982

1.620

4.040

4.040

4.520

4.520

4.520

4.520

4.520

4.780

4.780

4.780

4.720

4.720

4.680

4.680

4.680

4.680

4.680

4.600

4.600

4.600

6.830

6.940

7.020

7.090

7.080

3.820

3.820

3.820

3.980

3.980

3.980

3.980

0.784

1.960

1.960

1.890

1.890

1.890

1.890

1.890

1.850

1.850

1.850

1.880

1.880

1.910

1.910

1.910

1.910

1.910

1.810

1.810

1.810

2.650

2.690

2.710

2.750

2.760

1.580

1.580

1.580

0.308

0.771

0.771

0.751

0.751

0.751

0.751

0.751

0.726

0.726

0.726

0.730

0.730

0.731

0.731

0.731

0.731

0.731

0.705

0.705

0.705

1.030

1.050

1.060

1.070

1.060

0.614

0.922

2.300

2.300

2.400

2.400

2.400

2.400

2.400

2.410

2.410

2.410

2.360

2.360

2.380

2.380

2.380

2.380

2.380

2.330

2.330

2.330

3.500

3.500

3.510

3.510

3.510

1.940

1.550

3.880

3.880

3.770

3.770

3.770

3.770

3.770

3.670

3.670

3.670

3.710

3.710

3.740

3.740

3.740

3.740

3.740

3.570

3.570

3.570

5.310

5.370

5.400

5.510

5.580

3.220

0.426

1.070

1.070

1.040

1.040

1.040

1.040

1.040

1.010

1.010

1.010

1.020

1.020

1.030

1.030

1.030

1.030

1.030

0.981

0.981

0.981

1.460

1.470

1.480

1.510

1.530

0.884

0.884

0.884

0.890

0.890

0.890

0.890

0.000

0.000

0.000

195.0

195.0

195.0

190.0

190.0

190.0

190.0

190.0

185.0

185.0

185.0

187.0

187.0

188.0

188.0

188.0

188.0

188.0

180.0

180.0

180.0

188.0

187.0

186.0

188.0

190.0

177.0

177.0

177.0

178.0

178.0

178.0

178.0

0.000

0.000

0.000

816.0

816.0

816.0

795.0

795.0

795.0

795.0

795.0

774.0

774.0

774.0

783.0

783.0

787.0

787.0

787.0

787.0

787.0

753.0

753.0

753.0

787.0

783.0

779.0

787.0

795.0

741.0

741.0

741.0

745.0

745.0

745.0

745.0

0.000

0.000

0.000

1.00

1.00

1.00

0.97

0.97

0.97

0.97

0.97

0.95

0.95

0.95

0.96

0.96

0.96

0.96

0.96

0.96

0.96

0.92

0.92

0.92

0.96

0.96

0.95

0.96

0.97

0.91

0.91

0.91

0.91

0.91

0.91

0.91

0.00

0.00

0.00

0.614 1 1.940 1 3.220

0.614 1.940 1 3.220

1.610

1.610

1.610

1.610

0.000

0.000

0.614

0.614

0.614

0.614

0.000

0.000

2.000

2.000

2.000

2.000

0.000

0.000

3.250

3.250

3.250

3.250

0.000

0.000

0.000 1 0.000

0.000 0.000

0.000 1 0.000 0.000 1 0.000 1 0.000 1 0.000

*All numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate + 2.5 mm

1) Initial coordinate of fuel is 10.5 mm

2) End coordinate of fuel is 172.5 mm

3) Current value per maximum value.

G-231
#B12T I lndivld#,i1 Ch • M4'i ofabricacd Rei Fluel Rods,",-,. I

SýeirraliatM WNi aed Cladding) under IGR T•ests •i I

Table G-12.3. Radial Energy Characteristics of Fuel Rod #1B12T

Coordinates of fuel zones (mm)

Characteristics* I zone 2 zone 3 zone 4 zone

1.2- 2.811 2.811-3.432 3.432-3.704 3.704-3.790

Number of fissions x 10"14 (fiss) 0.406 0.238 0.116 0.038

Power of fuel rod') (kW) 1.090 0.641 0.313 0.102

U235 Energy deposition2) (callg fuel) 55.10 53.80 52.60 51.30

Energy deposition 2

) (J/g fuel) 231.0 225.0 220.0 215.0

Energy deposition3) (per-unit) 1.000 0.976 0.955 0.931

Number of fissions x10"12 (fiss) 1.800 1.040 0.495 0.153

Power of fuel rod') (kW) 0.048 0.028 0.0 13 0.004

U238 Energy deposition 2

) (caVg fuel) 2.420 2.330 2.210 2.050

Energy deposition2 ) (J/g fuel) 10.10 9.750 9.250 8.580

Energy deposition3

) (per-unit) 1.000 0.963 0.913 0.847

Number of fissions x 10"14 (fiss) 0.563 0.382 0.262 0.148

Power of fuel rod') (kW) 1.570 1.060 0.729 0.413

Pu239 Energy deposition2

) (cal/g fuel) 79.10 89.50 123.0 209.0

Energy deposition2

) (J/g fuel) 331.0 375.0 515.0 875.0

Energy deposition3

) (per-unit) 0.378 0.428 0.589 1.000

Number of fissions x10.-3 (fiss) 2.090 1.480 1.060 0.633

Power of fuel rod') (kW) 0.570 0.404 0.290 0.173

Pu241 Energy deposition2) (caVg fuel) 28.80 34.10 48.80 87.50

Energy deposition2) (J/g fuel) 121.0 143.0 204.0 366.0

I Energy deposition3

) (per-unit) 0.329 0.390 0.558 1.000

Number of fissions xlO" (fiss) 0.802 0.508 0.302 0.143

Other Power of fuel rod') (kW) 0.002 0.001 0.001 0.000

isoto- Energy deposition2) (cal/g fuel) 0.111 0.118 0.140 0.198

pes Energy deposition2) (J/g fuel) 0.460 0.490 0.590 0.830

Energy deposition3) (per-unit) 0.561 0.596 0.707 1.000

Number of fissions x 10"*4 (fiss) 1.200 0.779 0.489 0.250

Power of fuel rod') (kW) 3.290 2.140 1.340 0.687

Total Energy deposition2) (cal/g fuel) 166.0 180.0 226.0 347.0

Energy deposition2

O (J/g fuel) 695.0 753.0 946.0 1453.

Energy deposition3) (per-unit) 0.478 0.519 0.651 1.000

I) at time of 2.90 s, 2) at infinite time, 3) Current value per maximum value.

* All numerical values of characteristics were calculated for undamaged part or fuel stack only (See Table C.2.3.)

G-232
#B12T n • tki•:d•] c0f Refabried Fuel Rods

(VQt 'irrffiated Cladding)' indei IGR Tests

Table G-12.4. Fuel Enthalpy Vs. Time Calculated by FRAP-T6 Code for Fuel Rod #B12T

Time Enthalpy at fuel radius Fuel 1) t Energy deposition

T(ELY fuel) D in fuel rod

(S) 1.20 mm 2.82 mm1 3.47 nmm 3.79 mm cag fud J/grfuel cal/g fuel Jgrfuel

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

1.11

10.7

17.9

30.3

30.3

53.5

92.5

118

135

146

152

155

157

158

158

158

157

156

155

154

154

153

151

149

146

144

138

96.6

0.00 1 0.00

1.10

10.5

17.5

29.5

29.5

52.2

90.0

113

127

135

141

144

145

146

145

145

145

144

144

143

143

142

141

140

138

137

132

94.6

1.05

9.89

16.4

27.2

27.2

47.7

79.0

94.8

111

124

130

133

134

134

134

134

134

134

134

134

134

134

133

132

132

131

127

92.7

0.00

1.00

9.12

14.8

23.9

23.9

40.5

62.9

75.8

106

118

123

125

126

127

128

128

128

129

129

129

129

129

129

128

128

127

123

91.6

0.00

1.09

10.3

17.3

28.9

28.9

50.9

86.7

108

125

135

141

144

145

146

146

146

145

145

144

144

144

143

142

..140

139

137

132

94.6

0.00

4.55

43.3

72.3

121

121

213

363

453

523

566

590

602

608

611

611

611

609

607

605

602

602

599

593

587

581

575

552

396

0.00

1.30

12.0

19.9

33.1

33.1

57.5

97.5

123

141

151

158

162

165

167

169

169

170

171

172

172

172

173

174

174

175

175

177

182

0.00

5A6

50.5

83.2

138

138

241

409

516

589

633

661

679

690

700

707

707

712

716

719

722

722

724

728

731

733

735

742

761

Radial enthalpy distribution and fuel enthalpy are presented at elevation 18.6 mn

Ma'xdmum value of fuel enthalpy is 145.7 cal/g fuel (t-4.70 s)

1) All numnerical values ame presented at elevation %ith peak pow-T

G-233
i nividual di~ctofefbiac Fuel RSOT #B12T iO M Claddin) trder IGR TestsTable G-12.5. Energy Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for

Fuel Rod #B12T

Time Energy Linear Fuleta"1 Clad-to-coolant heat

Tim eLiposi nFuel enthalpy Leakage of energy') transfer coefficient1 a)

(s) (cal/g fuel) (kW/m) (calkg fuel) (ca/g fuel) W/m 2K)

SFAP-T6 SCANAIR FRAP-T6 SC FRAP-T6 SCA

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

42

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

1.36

12.6

20.7

34.5

34.5

60.0

102

129

147

158

165

169

172

175

176

176

178

178

179

180

180

181

181

182

183

183

185

190

0.00

5.88

45.4

74.2

130

130

249

296

205

126

76.9

48.5

31.9

21.9

14.5

102

102

7.70

6.28

5.21

4.39

4.39

3.76

2.87

2.32

1.96

1.70

1.21

0.17

0.00

1.09

10.3

17.3

28.9

28.9

50.9

86.7

108

125

135

141

144

145

146

146

146

145

145

144

144

144

143

142

140

139

137

132

94.6

0.00

1.15

10.5

15.6

23.3

35.4

55.6

84.0

0.00

0.00

0.00

0.01

0.02

0.02

0.04

0.11

0.24

0.47

0.76

1.10

1.49

1.93

2.56

3.26

3.26

4.02

4.83

5.68

6.56

6.56

7.47

9.36

11.3

13.3

152

23.0

76.8

0.00

0.00

0.00

0.01

0.02

0.03

0.05

0.12

0.00

0.01

0.01

0.01

0.01

0.01

0.02

0.04

0.06

0.07

0.08

0.09

0.10

0.11

0.12

0.12

0.12

0.13

0.14

0.14

0.14

0.14

0.15

0.15

0.15

0.15

0.15

0.15

0.09

0.00

0.01

0.01

0.01

0.01

0.02

0.02

0.04

a a. A. I I a.

) All numicat valucs am prcs•-nted at clevkion with pea1k p er

G-234
#B12T ivid~Tl5~~!Estic 1of Refý'*abiatdFeRos1" #B 12 T hidaed Claddiig) •un•d IGR Tests.

Table G-12.6. Temperature Variation, Fission Gas Release and ZrO2 Thickness Vs. Time for Fuel

Rod #B12T Calculated by FRAP-T6 and SCANAIR Codes

Fuel centerline Fuel surface Clad outer

Time temperature') temperature') ' temperature') Fission gas release

(s) . (K (K) Q9 _ (Y)

FRAP-T6 IjSCANAIR FRAP-T6 I SCANAIR FRAP.T6_I SCANAIR FRAP-T6 SCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

52

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

313

465

573

747

747

1060

1562

1871

2068

2178

2238

2271

2288

2296

2296

2296

2291

2283

2274

2263

2263

2252

2229

2206

2184

2163

2091

1613

293

312

460

537

649

818

1092

1470

293

311

442

527

657

657

886

1184

1351

1725

1867

1923

1949

1962

1975

1984

1984

1990

1994

1996

1998

1998

1998

1996

1991

1984

1975

1935

1551

293

310

442

508

601

739

946

1193

293

301

376

434

532

532

694

979

1188

1297

1346

1403

1458

1507

1557

1595

1595

1626

1650

1669

1684

1684

.1696

1712

1721

1726

1727

1711

1409

293

302

380

424

490

589

748

990

0.00

0.02

0.05

0.08

0.13

0.13

0.26

0.77

3.11

4.59

5.68

6.49

7.25

7.27

8.64

10.3

10.3

11.9

13.0

13.6

13.9

13.9

14.2

15.0

15.6

15.6

15.7

15.7

16.0

0.00

0.15

0.93

1.19

1.69

2.17

2.65

3.06

_____________ I I 1. 6 .

G-235
.gdvdulC cIf~ti~ffabricaied Fue~l Rods #B 2 Cdlladdlrig) under IGR Tests"-

Table G-12.7. Mechanical Characteristics of Fuel Rod #B12T Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes

T Clad outer Fuel hoop Fuel - clad gap Clad hoop Clad hoop Internal gas

temperature" strain" width' strain) stress") pressure (s) (K) (0% (mm J (t%) (MPa) (MPa)

FRAP-T6 SCANAIR FRAAT6-SC FRAP.T61SCAN FRAP-T61SC FRAP-T6 SCANAIR FRAP-T61SCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

301

376

434

532

532

694

979

1188

1297

1346

1403

1458

1507

1557

1595

1595

1626

1650

1669

1684

1684

1696

1712

1721

1726

1727

1711

1409

293

302

380

424

490

589

748

990

0.00

0.04

0.22

0.36

0.58

0.58

1.03

1.87

2.67

3.30

3.72

3.92

4.08

4.25

4.29

4.42

4.42

4.61

4.87

4.89

4.83

4.83

4.88

4.86

4.78

4.70

4.62

4.33

2.65

0.00

0.01

0.12

0.18

0.27

0.42

0.69

1.13

0.03

0.03

0.02

0.02

0.01

0.01

0.00

0.00

0.00

2.49

2.47

2.46

2.46

2.45

2.45

2.44

2.44

2.44

2.43

2.42

2.43

2.43

2.43

2.43

2.43

2.43

2.44

2A5

2.51

0.03

0.03

0.01

0.01

0.01

0.01

0.03

0.03

0.03

0.02

0.02

0.01

0.07

0.11

0.17

0.17

0.29,

0.99

1.64

65.0

65.0

65.1

65.1

65.2

65.2

65.3

65.3

65.3

65.3

65.3

65.4

65.4

65.4

65.4

65.4

65.4

65.4

65.4

65.1

0.08

0.11

0.16

0.24

0.36

0.55

8.41

8.50

8.97

9.18

9.42

9.42

9.71

37.2

10.6

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

8.14

8.24

8.82

9.03

9.28

9.55

9.85

10.0

1.70

1.72

1.81

1.85

1.89

1.89

1.95

2.01

2.06

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

1.70

1.72

1.81

1.85

1.88

1.92

1.96

2.00

I _________ I .L.....~.L J. I

" AJI numerical values arc presented at ele•ation vith peak povmr

G-236
#B12T Jd___ Cteristics of RefbriatdFulRos

(Preirad e)'~erritdiiied Cladd ing uder IGR Tests:

Table G-12.8. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #B12T

Axial interval Energy deposition at infinite time Fuel enthalpy

from-to at time (t=4.70 s)

(mm)-(mm) cal/g fuel Jig fuel per-unit cal/g fuel J/g fuel per-unit

10.5-26.7 194 812 1.00 146 611 1.00

26.7 -42.9 190 796 0.98 143 599 0.98

42.9-59.1 187 781 0.96 140 588 0.96

59.1 - 75.3 187 782 0.96 140 589 0.96

75.3-91.5 188 788 0.97 141 593 0.97

91.5-107.7 183 767 0.94 138 577 0.94

107.7- 123.9 185 776 0.96 139 584 0.96

123.9 - 140.1 186 781 0.96 140 588 0.96

140.1 - 156.3 177 743 0.91 133 559 0.91

156.3 - 172.5 178 746 0.92 134 561 0.92

200

CE

160

E 120

CE.

- 80

0

p40

4)

---------- - - "- -- --- -.

.•e~el .e je~p. eo m~l...........e~

-Energy deposition

Fuel enthalpV

0

0 30 60 90

Axial coordinate (mm)

120 150 180

Fig. G-12.5. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6 Code

for Fuel Rod #B12T

G-237
#B12T k lted Cladding)und'e-rIGR Tests-.-,

1.2-

S 1.0-

0.8 .

0.6

0.2

2 3 4

Radial fuel coordinate (mm)

1.2

pun'

U 1.0 -

0.8

0.6-

0.2-

1 4

Radial fuel coordinate (mm)

Fig. G-12.6. U235 and Pun' Radial Distributions of Energy Deposition for Fuel Rod #B12T

G-238
#B12T S'lgof Refabricatd Fuel Rds'."

I (PetrzJi~)1~1Peiradite Claidding)uinder IOR Tests

1.2

0

1.0

0.8

0.6

.4 4-

1-

r0.4 -1- TY

3

02-

1 2 4

Radial fuel coordinate (mim)

200

160

• 120

. 80

40

0

1.0 1.5 2.0 2.5 3.0 3.5

Radial fuel coordinate (mm)

4.0

Fig. G-12.7. Radial Distributions of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #B12T

G-239
#B12T

300

240

•180

c'120.

60

0

-FRAP-T6 

-120

SCANAIR 

c

Powdr Of fuel rodR"aFlR

Enerdy depositionuT 

s

Fuel nthaipy 

80 -0

L-eakage of energy

Clad Oxidation en

5 6 7 8 9 10

Time (s)

2500

2000

' 1500.

E100o

500

0- 1 5 6 7 8 9 10

Time (s)

Fig. G-12.8. Energy and Temperature Characteristics Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes for Fuel Rod #BI2T

G-240
#B12T I Indivan ' 0 ev tcsof Refabric6t Fuel Rods ... . I

I (Prie'4## cirradialed Cladding)-underi IGR Tests

2.5

2.0

1 .5

0.5

0.0

100

80

6o

0

40 ,=

60~

20

0

.!

0 1 2 3 4 5 6 7 8 9 10

Time (s)

100

80

60

40

0.

0

0

FRAP-T6 .... SCANAIR

-'I*- Clad hoop strain

---- Fuel-clad a width

3.0

2.4

1.8

0.6

0.

•0

0.6

0.0

20

0

0 1 2 3 5 6 7 8 9 10

Time (s)

Fig. G-12.9. Cladding Mechanical Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #B12T

G-241
#B12T lni15dii M"M i, Fuel% Rods 

~(rerrdi ~j~~'i~cdClaidding) tinde IG'R'i Tes~ts ,"

5-

4

•0

0:

16

14

12

c 10

I.:.

S6

4

2

0

2500

2000

4.

1500

E

1000 *

C

.)

U

500

0

0 1 2 3 4 5 6 8 9 10

Time (s)

0- 2 4 6 8

Time (s)

10

Fig. G-12.10. Fuel Strain and Fission Gas Release Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #B12T

G-242
I zii~T~~~stcsofRe& bricated F u el Rd' #B12T elirdi~d Cladding),uwider' IGR Tests"

Table G-12.9. Some Results of PIE for Fuel Rod #BI2T

Characteristic Value

1. Measured parameters of cladding oxidation and cladding

deformation

1.1. Cladding thickness at elevation 85, 140 mm correspondent to

different azimuthal angles (pm):

00 700 649

900° 677 R

1800 634 634

2700 677 677

1.2. ZrO2 thickness at elevation 85, 140 mm correspondent to different

azimuthal angles (pm):

00 10 10

900 15 -

1800 10 15

2700 10 10

1.3. aZr(O) thickness at elevation 85, 140 mm correspondent to

different azimuthal angles (pm):

00 10 10

900 25 -

1800 10 10

2700 10 10

1.4. Clad hoop strain at elevation 85, 140 mm, respectively (%) 6.3 24

2. Measured parameters for FGR analysis

2.1. Internal gas composition (% by volume):

He

N2

02

Ar

C0 2

Kr

Xe

22. Free gas volume (cm3)

2.3. Gas pressure inside fuel rod under normal condition (MPa)

2.4. Kr concentration in fuel (cm 3

/g fuel)

3. Measured parameters of cladding hydriding

3.1. Coefficient of hydride orientation (per-unit)

3.2. Hydrogen concentration (% by weight)

G-243
#B12T Individual C, "Rhfabricate~l Fuel Rods

[ errdiat• .•u• • ed Cladding) under IGR Tests

Table G-12.10. General Characteristic of Fuel Rod #B12T

Parameter Unit Value

Experiment FRAP-T6 SCANAIR

I Type of coolant air air air

2 Burnup MWd/kg U 48.7 48.7 48.7

3 Energy deposition in fuel rod cal/g fuel 186 186 186

4 Peak fuel enthalpy cal/g fuel - 146 -

5 Peak fuel temperature K - 2296 -

6 Peak clad temperature K - 1727 -

7 Fuel rod failure Yes, No Yes Yes -

8 Type of failure:

- cladding rupture due to ballooning Yes, No Yes Yes

- cladding rupture due to PCMI Yes, No No No

- fragmentation of fuel rod Yes, No No --

9 Failure time s - 3.33 -

10 Fuel enthalpy at failure callg fuel - 119 -

11 Outer cladding temperature at failure K - 1285 -

12 Internal gas pressure at failure MPa - 2.05 -

13 ZrO2 thickness after test Pm 10-15 --

14 Residual clad hoop strain:

- peak value for ballooning area % 24.0 64.66 -

- other location') % 6.3 3.48 -

Kr concentration in internal gas % by volume - 2.11 - composition after test

16 Xe concentration in internal gas % by volume 12.65

composition after test % by volue_1265_

17 Kr concentration in fuel after test cm 3

/g fuel 0.14 -

')Calculated values by FRAP-T6 and SCANAIR codes are average along height or fuel rod excluding ballooning region

G-244
"Individta( Characterstics foriFueJ 13 y' r,-GR'-4.' .. 

--- ------------

G-245
#B13T (Preiffdatn Ficreimidiate Cladding) widerJ 16, t

I I

Fig. G-13.1. Appearance of Fuel Rod #B13T (photographs and X-ray photograph)

G-246
#B13T

F~]

Position'3

Fig. G-13.2. Cross-Section and Cladding Microstructure for Fragment of Fuel Rod #B13T

G-247
#B13T IndividuaJ oh.da: i• Refabricated Fuel R~dls -?

'(FPreirradiated Fui u ?.S"diataed Cladding)under IGRTess *•':

Table G-13.1. Time Dependent Energy Characteristics of Fuel Rod #BI3T

Reac- Cumulative number of fissions Power Energy

tor in fuel rod (fiss) of fuel deposition

Time energy rod in fuel rod

(s) deposi- U 235 U 238 Pu23 9 Pu24' Other Total (kV) cal/g J/g fuel

tiont) xlO 14 xI0-3 xI0"1 4 xlO-14 iso- X10" 14 fuel

(%) topes

xlO-n

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

9.0

10.0

20.0

30.0

cO

0.000

0.680

4.090

6.020

9.140

14.30

23.00

36.50

53.30

68.60

79.50

85.90

89.30

91.10

92.20

92.90

93.50

94.00

94.50

94.90

95.30

95.60

95.90

96.30

96.70

97.00

97.20

97.60

97.90

99.20

99.60

100.0

0.000

0.085

0.512

0.755

1.150

1.790

2.880

4.570

6.680

8.590

9.970

10.80

11.20

11.40

11.60

11.60

11.70

11.80

11.80

11.90

11.90

12.00

12.00

12.10

12.10

12.10

12.20

12.20

12.30

12.40

12.50

12.60

0.000

0.027

0.161

0.237

0.360

0.564

0.904

1.440

2.100

2.700

3.130

3.380

3.520

3.590

3.630

3.660

3.680

3.700

3.720

3.740

3.750

3.760

3.770

3.790

3.810

3.820

3.830

3.840

3.850

3.900

3.920

3.950

0.000

0.109

0.655

0.964

1.460

2.290

3.680

5.840

8.530

11.00

12.70

13.80

14.30

14.60

14.80

14.90

15.00

15.10

15.10

15.20

15.30

15.30

15.30

15.40

15.50

15.50

15.60

15.60

15.70

15.90

15.90

16.10

0.000

0.037

0.223

0.328

0.498

0.780

1.250

1.990

2.900

3.740

4.330

4.680

4.870

4.960

5.020

5.060

5.100

5.120

5.150

5.170

5.190

5.210

5.220

5.250

5.270

5.280

5.290

5.320

5.330

5.400

5.420

5.470

0.000

0.118

0.707

1.040

1.580

2.470

3.970

6.310

9.210

11.80

13.70

14.90

15.40

0.000

0.234

1.410

2.070

3.140

4.930

7.900

12.60

18.30

23.60

27.40

29.60

30.70

15.70 1 31.30

15.90

16.10

16.20

16.20

16.30

16.40

31.70

32.00

32.20

32.30

32.50

32.70

0.000

1.340

7.540

11.90

19.50

32.60

53.90

78.70

82.30

66.20

42.10

22.80

12.00

6.890

4.530

3.410

2.870

2.600

2.400

2.110

1.790

1.530

1.320

0.960

0.741

0.602

0.510

0.437

0.350

0.091

0.048

0.001

0.000

2.680

16.10

23.80

36.10

56.50

90.60

144.0

210.0

271.0

314.0

340.0

353.0

360.0

365.0

368.0

370.0

373.0

375.0

376.0

378.0

379.0

380.0

383.0

384.0

386.0

387.0

389.0

390.0

397.0

400.0

408.0

0.000

11.20

67.40

99.60

151.0

237.0

379.0

603.0

879.0

1134.

1314.

1423.

1478.

1507.

1528.

1540.

1549.

1561.

1570.

1574.

,01582.

1586.

1591.

1603.

1607.

1616.

1620.

1628.

1633.

1662.

1674.

1708.

16.50 I 32.80

16.50

16.60

16.60

16.70

16.80

16.80

16.90,

16.90

17.10

17.20

17.30

32.90

33.00

33.10

33.30

33.40

33.40

33.60

33.70

34.10

34.20

34.50

Maximum value of power is 84.2 kW (t - 3.10 s).

1) Current energy deposition per maximum energy deposition (at infinite time)

G-248
#B13T I 1ndiiidtiMi.rnýfristies of Refabric'atied Fuel ds27 I(P~reirrdnk~f*ýPreirradiat~l Claddingj) uid6*I Res.

Table G-13.2. Axial Energy Characteristics of Fuel Rod #BI3T

Axial Cumulative number of fissions Maxi- Energy deposition

coordi- at axial interval (fiss) mum at infinite time*

fate u 235 U238 pu239 Pu 24 O powerof from Other Total fuerod cal/g J/g perlower xl0"13 x10"1 X10-13 x10"13 iso- x-0"13 (W) fuel fuel unit3 )

end of topes t=3.1Os

fuel rod x 10"10

(mm)

10.0

15.0

20.0')

25.0

30.0

35.0

40.0

45.0

50.0

55.0

60.0

65.0

70.0

75.0

80.0

85.0

90.0

95.0

100.0

105.0

110.0

115.0

120.0

125.0

130.0

135.0

140.0

145.0

150.0

155.0

160.0

165.0

170.0

175.02)

180.0

185.0

0.000

0.000

2.440

4.140

4.200

4.220

4.440

4.500

4.220

4.050

4.070

4.050

3.930

4.060

4.220

4.140

4.210

4.400

4.450

4.440

4.440

4.360

4.340

4.320

4.310

4.390

4.380

4.430

4.460

4.520

2.130

2.130

2.130

1.280

0.000

0.000

0.000

0.000

7.910

13.20

13.40

13.50

14.20

14.70

13.80

13.20

13.30

13.30

12.90

12.80

13.30

13.30

13.50

13.70

13.80

13.90

13.90

13.90

13.80

13.70

13.70

13.60

13.60

13.60

13.70

13.60

5.610

5.610

5.610

3.370

0.000

0.000

0.000

0.000

3.180

5.330

5.420

5.450

5.750

5.910

5.550

5.320

5.350

5.350

5.200

5.170

5.360

5.380

5.460

5.530

5.580

5.620

5.620

5.610

5.590

5.550

5.520

5.510

5.500

5.520

5.560

5.530

2.590

2.590

2.590

1.550

0.000

0.000

0.000

0.000

1.100

1.820

1.850

1.860

1.970

2.040

1.910

1.830

1.840

1.850

1.800

1.760

1.820

1.840

1.870

1.870

1.890

1.900

1.900

1.920

1.910

1.890

1.880

1.870

1.860

1.860

1.870

1.850

0.850

0.850

0.850

0.510

0.000

0.000

0.000

0.000

3.620

6.000

5.980

5.970

5.960

5.940

5.940

5.940

5.960

5.960

5.960

5.970

5.980

5.980

6.000

6.010

6.010

6.010

6.010

6.000

5.990

5.980

5.960

5.930

5.890

5.850

5.790

5.740

2.540

2.540

2.540

1.520

0.000

0.000

0.000

0.000

6.800

11.40

11.60

11.70

12.30

12.60

11.80

11.30

11.40

11.40

11.10

11.10

11.50

11.50

11.70

11.90

12.10

12.10

12.10

12.00

12.00

11.90

11.90

11.90

11.90

11.90

12.00

12.00

5.620

5.620

5.620

3.370

0.000

0.000

0.000

0.000

1.660

2.790

2.830

2.850

3.000

3.070

2.890

2.770

2.780

2.780

2.700

2.720

2.820

2.810

2.850

2.910

2.940

2.950

2.950

2.940

2.920

2.900

2.890

2.900

2.900

2.910

2.930

2.940

1.370

1.370

1.370

0.823

0.000

0.000

0.000

0.000

405.0

407.0

407.0

406.0

406.0

404.0

404.0

404.0

404.0

403.0

403.0

409.0

409.0

405.0

405.0

411.0

411.0

409.0

409.0

407.0

407.0

407.0

408.0

410.0

410.0

412.0

412.0

415.0

417.0

417.0

417.0

417.0

0.000

0.000

0.000

0.000

1695.

1704.

1704.

1700.

1700.

1691.

1691.

1691.

1691.

1687.

1687.

1712.

1712.

1695.

1695.

1720.

1720.

1712.

1712.

1704.

1704.

1704.

1708.

1716.

1716.

1725.

1725.

1737.

1746.

1746.

1746.

1746.

0.000

0.000

0.00

0.00

0.97

0.98

0.98

0.97

0.97

0.97

0.97

0.97

0.97

0.97

0.97

0.98

0.98

0.97

0.97

0.99

0.99

0.98

0.98

0.98

0.98

0.98

0.98

0.98

0.98

0.99

0.99

0.995

1.00

1.00

1.00

1.00

0.00

0.00 I I

* All numerical values of characteristics are presented as average values at the length int;rval equal to the axial coordinate + 2.5 mm

I) Initial coordinate of fuel is 19.5 mm

2) End coordinate of fuel is 175.5 mm

3) Current value per maximum value.

G-249
#B13T 1Priirdiatedu Chrc"jt~~Reabfi~cateda Fu~el R-odsj> I (PreirFdiated F !mi~,?d-iated Clading) u~e Gfei

Table G-13.3. Radial Energy Characteristics of Fuel Rod #B13T

Coordinates of fuel zones (mm)

Characteristics* 1 zone 2 zone 3 zone 4 zone

1.2 -2.811 2.811-3.432 3.432-3.704 3.704-3.790

Number of fissions x 10"t4 (fiss) 5.970 3.530 1.740 0.569

Power of fuel rod') (kW) 14.30 8.460 4.170 1.360

U235 Energy deposition2) (cal/g fuel) 147.0 145.0 143.0 140.0

Energy deposition2) (J/g fuel) 615.0 607.0 599.0 586.0

Energy deposition3) (per-unit) 1.000 0.986 0.973 0.952

Number of fissions x 10"1' (fiss) 19.40 11.20 5.290 1.640

Power of fuel rod') (kW) 0.459 0.264 0.125 0.039

U238 Energy deposition2 ) (cal/g fuel) 4.720 4.530 4.290 3.990

Energy deposition2) (J/g fuel) 19.80 19.00 18.00 16.70

Energy deposition3) (per-unit) 1.000 0.960 0.909 0.845

Number of fissions x 10"t (fiss) 6.250 4.260 2.940 1.690

Power of fuel rod') (kW) 15.50 10.50 7.280 4.190

Pu239 Energy deposition2 ) (caVg fuel) 160.0 181.0 250.0 432.0

Energy deposition2) (J/g fuel) 670.0 758.0 1047. 1808.

Energy deposition3) (per-unit) 0.370 0.419 0.579 1.000

Number of fissions x10-13 (fiss) 20.20 14.50 10.50 6.350

Power of fuel rod') (kW) 4.930 3.530 2.560 1.550

Pu241 Energy deposition2) (calfg fuel) 50.80 60.60 87.70 159.0

Energy deposition2 ) (J/g fuel) 213.0 254.0 367.0 666.0

Energy deposition3) (per-unit) 0.319 0.381 0.552 1.000

Number of fissions x 10-" (fiss) 7.490 4.760 2.830 1.350

Other Power of fuel rod') (kW) 0.018 .0.012 0.007 0.003

isoto- Energy deposition2 ) (caVg fuel) 0.189 0.200 0.238 0.340

pes Energy deposition2 ) (J/g fuel) 0.790 0.840 1.000 1.420

Energy deposition3) (per-unit) 0.556 0.588 0.700 1.000

Number of fissions x10-" (fiss) 14.50 9.360 5.790 2.910

Power of fuel rod') (kW) 35.30 22.80 14.10 7.110

Total Energy deposition2 ) (cal/g fuel) 363.0 391.0 484.0 731.0

Energy deposition2) (J/g fuel) 1520. 1637. 2026. 3060.

Energy deposition3 ) (per-unit) 0.497 0.535 0.662 1.000

1) at time of 3.10 s, 2) at infinite time, 3) Current value per maxdmum value.

0 All numerical values of characteristics were calculated for undamaged part of fuel stack only (See Table C.2.3.)

G-250
#B13T ii4i a A 'h=isieof Re'fkbrici~d JFuelý Rod~s *- .1: I (Pr~ei~nadt; Preiffiadiated Claditing) unider TR Tests'~

Table G-13.4. Fuel Enthalpy Vs. Time Calculated by FRAP-T6 Code for Fuel Rod #B13T

Time Enthalpy at fuel radius Fuel enthalpy Energy deposition

Tm(gfuel) Fuel entfal in fuel rod

(s) 1.20 mm 2.82 mm 3.47mm 3.79mm __alg 11=1 I___fue calgfucl J/g fuel

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

2.56

15.0

22.1

33.5

52.6

84.4

134

196

253

0.00

2.55

14.8

21.8

33.1

52.0

83.4

132

191

247

0.00

2.48

142

20.9

31.A

48.5

75A

111

176

233

0.00

2.37

13.4

19.4

28.5

41.9

60.7

74.9

163

210

0.00

2.53

14.6

21.5

32.6

50.8

80.6

125

188

243

0.00

10.6

61.4

90.3

137

213

338

523

787

1020

0.00

2.69

16.2

23.8

36.2

56.7

90.9

144

211

271

314

340

353

361

365

368

371

373

375

377

378

379

381

383

385

386

387

390

400

0.00

11.3

67.8

99.9

152

237

381

605

883

1136

1317

1424

1480

1511

1529

1542

1553

1562

1570

1578

1584

1590

1595

1604

1611

1617

1622

1636

1678 .3. _____________ .3. .L I I _____________ J

Radial enthalpy distribution and fuel enthalpy are presented at elevation 167.7 mm

Maximum value of fuel enthalpy is 243.5 cal/g fuel (t-3.40 s)

"• All numerical values are presented at elevation with peak poiwr

G-251
indaivid~ual C~h'a ruAetstsotr Aetabric~atd' Fuel Rods 3⁄4 #B1131T (I a FU 1.. g.i Idiated Cladding)under IGR-Tests:-

Table G-13.5. Energy Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for

Fuel Rod #B13T

Time Energy Linear F 1 L) Clad-to-coolant heat

(s) deposition') Po~r') Fuel enthalpy/g Leakage of energyl) transfer coefficient')

(cal/g fuel) (kW/m) (cal/g fuel) (cal/g fuel) (kW/m2K)

FRAP-T6 SC' FRAP-T6 SCANAIR FRAP-T6 SCAAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

* 0.00

2.74

16.5

24.3

36.8

57.7

92.5

147

214

276

320

346

359

367

371

375

377

379

381

383

385

386

387

390

391

393

394

397

409

0.00

9.76

55.0

86.8

142

238

393

573

598

481

305

165

87.0

50.0

32.9

24.8

20.9

18.9

17.4

15.3

13.0

11.1

9.59

6.98

5.39

4.38

3.71

2.55

1.23

0.00

2.53

14.6

21.5

32.6

50.8

80.6

125

188

243

0.00

2.42

14.1

20.8

31.5

49.3

78.8

124

0.00

0.00

0.01

0.01

0.02

0.03

0.07

0.18

0.42

0.85

0.00

0.00

0.01

0.01

0.02

0.03

0.06

0.16

0.00

0.01

0.01

0.01

0.01

0.02

0.03

0.06

0.09

0.12

0.00

0.01

0.01

0.01

0.01

0.02

0.03

0.05

4 1 J. .4 . -

1) All numerical values are Presented at elevation imith peak power

G-252
#B13T (Prirada Iiejiradiated CIaddin') uiide IlGRTests

Table G-13.6. Temperature Variation, Fission Gas Release and ZrO2 Thickness Vs. Time for Fuel

Rod #B13T Calculated by FRAP-T6 and SCANAIR Codes

Fuel centerline Fuel surface Clad outer i Time tpe~e J tepatr 1 ) Fission gas release () temperaturel) temperaturel) temperatureO (%

(s) (K) (K) (K)

FRAP-T6 I SCANAIR FRAP-T6 SCANAIR FRAP-T6 IjSCANAIR FRAP-T6 ISCANAIR

.0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

337

530

632

791

1048

1461

2056

2632

3014

293

332

510

605

753

989

1367

1924

293

334

506

593

722

905

1155

1340

2346

2734

293

331

498

586

719

921

1215

1564

293

307

395

442

517

644

868

1171

1368

1596

293

306

389

434

504

621

818

1126

0.00

0.10

0.40

0.63

1.05

1.86

3.64

6.47

10.8

17.8

0.00

0.29

1.12

1.38

1.89

2.38

2.84

4.18

) All numerical values are presented at elevation With peak povwr

G-253
#B13T indiviuali Charad o-tf Refabrica ted' *Fi' Rbds "I

(Priiriidiaied FurjItreipnated Cladding) "inde" iGRTests

Table G-13.7. Mechanical Characteristics of Fuel Rod #B13T Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes

Clad outer Fuel hoop Fuel - clad gap Clad hoop Clad hoop Internal gas Time temperature') strain') width') strain') stress') pressure

(S) (K) (%) (mm) •(%) (MPa) (MPa)

FRAP.T61SCANAIR FRAP-T6ISC FRAP-T6 SCANAIR FRAP-T6 SCAN FRAP-T61SCANAI FRAP-T61SCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

.293

307

395

442

517

644

868

1171

1368

1596

293

306

389

434

504

621

818

1126

0.00

0.11

0.42

0.59

0.87

1.32

2.11

3.35

4.93

5.95

0.03

0.16

0.24

0.37

0.61

1.05

2.12

0.00 1 0.07

0.07

0.06

0.05

0.04

0.03

0.00

0.00

0.68

0.64

0.07

0.07

0.07

0.07

0.06

0.06

0.05

0.01

0.01

0.02

0.08

0.11

0.16

0.25

0.41

1.32

19.3

19.5

0.01

0.02

0.08

0.12

0.17

0.26

0.42

.0.58

8.97

9.20

9.83

10.1

10.3

10.7

11.1

13.9

0.00

0.00

8.70

8.92

9.59

9.83

10.1

10.5

10.8

10.7

1.70

1.74

1.85

1.89

1.94

2.00

2.08

2.18

0.10

0.10

1.70

1.74

1.85

1.88

1.93

1.97

2.02

2.07

30.0 I __________ I............I .L _________ .L A. I __________ I I __________ I __________ I

)All numicrical values arc prcscntcd a~t elevation iith Peak PO-v

G-254
#B13T Individual Chaiao_0tibfRefabricated Fuel Rods .

(Preirradiated FutCl1re~diated Cladding) under IGR Tests'.

Table G-13.7. Mechanical Characteristics of Fuel Rod #B13T Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes

.Clad outer Fuel hoop Fuel - clad gap Clad hoop Clad hoop Internal gas (s) temperature]) strainw) width') strain') stressi) pressure

(S) (K) (%) (mm) (%) (MPa) (MPa)

FRAP-T6 SCANAIR FRAP-T6 SCANAI I ISCANAI FRAP-T6TSCANAIR FRAP-T61SCANAIRI FRAP-T61SCANAIF

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

307

395

442

517

644

868

1171

1368

1596

293

306

389

434

504

621

818

1126

0.00

0.11

0.42

0.59

0.87

1.32

2.11

3.35

4.93

5.95

0.00

0.03

0.16

0.24

0.37

0.61

1.05

2.12

0.07

0.07

0.06

0.05

0.04

0.03

0.00

0.00

0.68

0.64

0.07

0.07

0.07

0.07

0.06

0.06

0.05

0.01

0.01

0.02

0.08

0.11

0.16

0.25

0.41

1.32

19.3

19.5

0.01

0.02

0.08

0.12

0.17

0.26

0.42

0.58

8.97

9.20

9.83

10.1

10.3

10.7

11.1

13.9

0.00

0.00

8.70

8.92

9.59

9.83

10.1

10.5

10.8

10.7

1.70

1.74

1.85

1.89

1.94

2.00

2.08

2.18

0.10

0.10

1.70

1.74

1.85

1.88

1.93

1.97

2.02

2.07

" All numerical values arc presented at elevation %ith peak pom-r

G-254
#B13T I individual'&MTedstics of Refabricated Fuel RO•:-ds I(Pieiirad.i -j--PrciIadiated Cladding) under IGR Tests

Table G-13.8. Axial Distribution of Energy Deposition and Fuel i" balpy Calculated by FRAP-T6

Code for Fuel Rod #B13T

Axial interval Energy deposition at infinite time Fuel enthalpy

from-to at time (t=3.40 s)

(mm)-(mm) caVg fuel J/g fuel per-unit cal/g fuel J/g fuel per-unit.

19.5-35.1 406 1701 0.97 239 1000 0.98

35.1-50.7 405 1697 0.97 238 996 0.98

50.7- 66.3 404 1692 0.97 237 991 0.97

66.3-81.9 406 1702 0.97 239 1000 0.98

81.9 -97.5 407 1706 0.98 - 237 994 0.97

97.5-113.1 409 1715 0.98 239 1000 0.98

113.1 - 128.7 407 1706 0.98 239 1000 0.98

128.7- 144.3 410 1717 0.98 239 1000 0.98

144.3- 159.9 414 1734 0.99 241 1010 0.99

159.9- 175.5 417 1747 1.00 243 1020 1.00

450

• 400

S350

300

o 250

200

0

1500

50

0.

.)

-0 100

nm 50

0

0 30 60 90 120 150

Axial coordinate (mm)

180

Fig. G-13.3. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6 Code

for Fuel Rod #B13T

G-255
#B13T Individual chrats bfRefabricated Fuel Rods

I(Preirradiated Fuci hated Cladding) under IGR Tests

1.2

E

@2

Cu

I

C

0

t

1.0 -

0.8 -

0.6 -

-1

2

Radial fuel coordinate (mm

u235

ill

0.4 -t--

0.2 -f1 3 4

1.2

In

0

1.0

0.8

0.6

0A

0.2

1 2 3

Radial fuel coordinate (mm)

Fig. G-13.4. U2 5 and Pu"9 Radial Distributions of Energy Deposition for Fuel Rod #B13T

4

G-256
#B13T IMdi'vidual•lb tteristics of Refabricated Fuel Rods

(Preirradi•f -l Preirradiated Cladding) under IGR Tests

1.2

0

*0

1.0

0.8

0.6

0.4

0.2

1 2 3 4

Radial fuel coordinate (mm)

160

140

120

100

- 80

• 60

2.0_ -- -- 3.0 s

40

20

0

1.0 1.5 2.0 2.5 3.0 3.5 4.0

Radial fuel coordinate (mm)

Fig. G-13.5. Radial Distributions of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #B13T

G-257
#B13T Individual Chamaoterlwssf Refabricated Fuel Roi.i

,(Preirradiated Fu[ýL- Wrdiated Cladding) under IGR Tests700

600

500

-a 400

a. 300 0

•- 200

100

0

3500

3000

2500

•,2000

rE 1500

1000

500

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

420

-360

-300

240 >

180 •

120 J

-60

0

0.14

0.12_ 0. 1 2ý

0

U

0.0460

0.02?

0.00

0 1 2 3 4 5 6 7 8 9 10.

Time (s)

Fig. G-13.6. Energy and Temperature Characteristics Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes for Fuel Rod #B13T

G-258
#B13T JIndiidual •ah teristics of Refabricated Fuel Rods

I (Preimrad,ýa , Preirradiated Cladding) under IGR Tests

2.5

2.0

1.5

C;

-0 1.0

E

0.5

0.0

100

80

60

40,

20)

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

25

20

._15

C.

0

0

-5

0

1.0

0.8

E

0.6 -E

to

10

0.4 .V

0.2

0.0

0 1 2 3 .4 5 6 7 8 9 10

Time (s)

Fig. G-13.7. Cladding Mechanical Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #B13T

G-259
#B13T indiviul •Ch'ac ir sb fRc fabricatwd Fuel Rods -" ' ' :.-- I

Preirn~iated Fue n--~radiated Cladding) under IGR Tests

10

8

aý

T.

0M

6

4

3500

2800

2100 E

a.

1400 •

U

700 2

0

20-

16

12

8

4

0

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

0 1 2 3 4 5

Time (s)

6 7 8 9 10

Fig. G-13.8. Fuel Strain and Fission Gas Release Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #B13T

G-260
#B13T I n'dividuil' Stc'isticsof Refabricated Fuel Rods I(Preirradiai• 57.Preiriadiated Cladding) under I•R Tests

Table G-13.9. General Characteristic of Fuel Rod #B13T

Parameter Unit Value

Experiment FRAP-T6 SCANAIR

I Type of coolant - air air air

2 Burnup MWd/kgU 41.0 41.0 41.0

3 Energy deposition in fuel rod callg fuel 408 408 408

4 Peak fuel enthalpy cal/g fuel - - -

5 Peak fuel temperature K - -

6 Peak clad tdmperature K - -

7 Fuel rod failure Yes, No Yes Yes -

8 Type of failure:

- cladding rupture due to ballooning Yes, No ? Yes -

- cladding rupture due to PCMI Yes, No ? No -

- fragmentation of fuel rod Yes, No Yes --

9 Failure time s - 3.05 -

10 Fuel enthalpy at failure cal/g fuel - 139 -

11 Outer cladding temperature at failure K - 1263 -

12 Internal gas pressure at failure MPa - 2.20 -

13 ZrO2 thickness after test tim - --

14 Residual clad hoop strain:

- peak value for ballooning area % - 18.92

- other location') % - -

Kr concentration in internal gas % by volume - 7.97

15 composition after test % by _____.e__7.9

16 Xe concentration in internal gas % by volume - 47.74

16 composition after test %_byvolume - 47.74

17 Kr concentration in fuel after test cm3

/g fuel - 0.11

')Calculated values by FRAP-T6 and SCANAIR codes are average along height offuel rod excluding ballooning region

G-261

St86b APPE-N

V6~144.P a

ticofoR! FIRTM

Iel PreIrr6 PO

lid aftEr? l1

jilt KC19F ME bf,ý"MM"k-
#H14T , 6dividuail Chiracid-ci-6s of Refabricated Fuel Rods -

(Fresh Fuel, Preifiaed'Cladding) under IGR Tests -

9.4

E

en

U

9.3

9.2

9.1

9.0

Axial coordinate (mm)

Fig. H-M.1. Appearance of Fuel Rod #H14T (photographs and X-ray photograph) and Profilometry

H-2
#H14T I lndivjdualfI•xristics of Refabricatcd Fuel Rods ,

[(Frn :Fui iatd Cladding) under IGR'Tests

Fig. H-1.2. Cross-Section and Cladding Microstructure for Fuel Rod #H14T at 85 mm Elevation

H-3
#H14T P;div i d uta~l ChtcoRc~fab~ricatdFu~el ,d

'(freshtFuci,,Priiý, fladding) under IGR Tes s.

Position I

El

Position2

Fig. H-1.3. Fuel Microstructure of Fuel Rod NH14T at 85 mm Elevation

H-4
#H14T I Ind~jwidu1 e tk6fýefabinjc'ated - Fiuel Rd

I(Fre Fu*W~ diatedCladdiniig'unde~r iGRTests?;-,' :

Table H-1.1. Time Dependent Energy Characteristics of Fuel Rod 8H14T

Reactor Cumulative number of fissions Power of Energy deposition

Time energy in fuel rod (fiss) fuel rod in fuel rod

(s) deposi- 233 u Total (kW) calig fuel J/g fuel

tN ( (oU) ) x10.11 xl0-12 xI0-14 xO~

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

9.0

10.0

20.0

30.0

co

0.000

1.080

4.330

5.280

6.420

7.880

9.930

13.10

18.60

28.20

42.40

58.20

71.30

80.10

85.50

88.80

90.80

92.20

93.10

93.90

94.50

94.90

95.30

96.00

96.50

96.90

97.10

97.60

97.90

99.20

99.60

100.0

0.000

0.083

0.332

0.405

0.493

0.605

0.762

1.010

1.430

2.160

3.250

4.470

5.470

6.140

6.560

6.810

6.970

7.070

7.140

7.200

7.250

7.280

7.310

7.370

7.400

7.430

7.450

7.490

7.510

7.610

7.640

7.700

0.000

0.030

0.118

0.144

0.175

0.215

0.271

0.358

0.508

0.767

1.160

1.590

1.940

2.180

2.330

2.420

2.470

2.510

2.540

2.560

2.570

2.590

2.600

2.620

2.630

2.640

2.650

2.660

2.670

2.700

2.720

2.740

0.000

0.083

0.334

0.407

0.494

0.607

0.765

1.010

1.440

2.170

3.270

4.480

5.490

6.170

6.580

6.830

6.990

7.100

7.170

7.230

7.270

7.310

7.340

7.390,-

7.430

7.460

7.480

7.510

7.540

7.640

7.670

7.730

0.000

0.468

0.955

1.110

1.370

1.830

2.700

4.430

7.780

13.00

17.30

16.20

11.80

7.510

4.540

2.800

1.830

1.280

0.958

0.754

0.617

0.519

0.425

0.289

0.210

0.161

0.131

0.109

0.084

0.021

0.010

0.000

0.000

0.950

3.810

4.650

5.650

6.930

8.740

11.60

16.40

24.80

37.30

51.20

62.70

70.50

75.30

78.20

80.00

81.30

82.20

82.90

83.40

83.90

84.30

85.00

85.50

85.80

86.10

86.60

87.00

88.60

89.20

91.10

0.000

3.980

15.90

19.50

23.70

29.00

36.60

48.60

68.70

104.0

156.0

214.0

262.0

295.0

315.0

327.0

335.0

340.0

344.0

347.0

349.0

351.0

353.0

356.0

358.0

359.0

360.0

363.0

364.0

371.0

373.0

381.0

Maximum value of power is 17.5 kW (t = 3.65 a)

I) Current energy deposition per maximum energy deposition (at infinite time)

H-5
#H14T i andividutI CharaifsticsbfRefabricated Fuiel Ros,:

(Freh FelPrei~3~addzig)uri& IR Tsts

Table H-1.2. Axial Energy Characteristics or Fuel Rod #HI4T

Axial Cumulative number of fissions Maximum Energy deposition

coordinate at axial interval (fiss) power of at infinite time*

from lower U235 U23 8 Total fuel rod cal/g fuel J/g fuel per-unit3 )

end of fuel x1O-13 X10" xl0-" (kW)

rod _ _ _ _ _ _ t=3.65 s

(mm)

30.0

35.0')

40.0

45.0

50.0

55.0

60.0

65.0

70.0

75.0

80.0

85.0

90.0

95.0

100.0

105.0

110.0

115.0

120.0

125.0

130.0

135.0

140.0

145.0

150.0

155.0

160.0

165.0

170.0

175.02)

180.0

0.000

2.870

3.110

3.030

2.960

2.880

2.810

2.760

2.740

2.690

2.670

2.640

2.640

2.630

2.620

2.610

2.610

2.610

2.610

2.630

2.610

2.630

2.630

2.640

2.670

2.690

2.710

2.730

2.760

0.823

.0.000

0.000

0.834

0.932

0.937

0.943

0.944

0.945

0.952

0.964

0.970

0.976

0.982

0.993

0.997

1.000

1.000

1.000

1.010

1.000

1.000

0.994

0.989

0.983

0.975

0.971

0.965

0.951

0.940

0.927

0.272

0.000

0.000

2.880

3.120

3.040

2.970

2.890

2.820

2.770

2.750

2.700

2.680

2.650

2.650

2.640

2.630

2.620

2.620

2.620

2.620

2.640

2.620

2.640

2.640

2.650

2.680

2.700

2.720

2.740

2.770

0.826

0.000

0.000

0.652

0.706

0.687

0.671

0.654

0.637

0.627

0.621

0.612

0.607

0.600

0.600

0.596

0.595

0.593

0.592

0.592

0.593

0.596

0.592

0.596

0.597

0.600

0.606

0.612

0.615

0.620

0.627

0.187

0.000

0.000

106.0

104.0

101.0

98.50

96.20

94.70

93.20

91.70

90.20

89.30

88.30

88.30

87.30

87.20

86.90

86.80

87.00

87.30

87.80

87.60

88.20

87.90

88.30

88.70

89.00

89.50

90.00

90.50

90.40

0.000

0.000

444.0

435.0

423.0

412.0

403.0

396.0

390.0

384.0

378.0

374.0

370.0

370.0

365.0

365.0

364.0

363.0

364.0

365.0

368.0

367.0

369.0

368.0

370.0

371.0

373.0

375.0

377.0

379.0

378.0

0.000

0.00

1.00

0.98

0.95

0.93

0.91

0.89

0.88

0.87

0.85

0.84

0.83

0.83

0.82

0.82

0.82

0.82

0.82

0.82

0.83

0.83

0.83

0.83

0.83

0.84

0.84

0.84

0.85

0.85

0.85

0.00 I I

All numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate ± 2.5 mm.

Initial coordinate of fuel is 33.0 mm.

2) End coordinate of fuel is 174.0 mm.

3) Current value per maximum value.

H-6
#H14T I Indjvjdt kiaccrjses~fhbnaieýd Fuel Riods: ' V

~(Fr eisM Fu l;T-iWed Claddinj' iciii IRTes k ::

Table H-1.3. Radial Energy Characteristics of Fuel Rod #H14T

Coordinates of fuel zones (mm)

Characteristics* 1 zone 2 zone 3 zone 4 zone

1.10-2.12 2.12-2.79 2.79-3.32 3.32-3.79

Number of fissions x10"t4 (fiss) 1.850 1.870 1.950 2.030

Power of fuel rod1) (kW) 4.190 4.240 4.400 4.590

U235 Energy deposition2) (cal/g fuel) 87.20 88.30 91.70 95.70

Energy deposition2) (J/g fuel) 365.0 370.0 384.0 401.0

Energy deposition3) (per-unit) 0.911 0.923 0.958 1.000

Number of fissions x10-12 (fiss) 0.684 0.695 0.688 0.669

Power of fuel rod') (kW) 0.015 0.015 0.015 0.015

U238 Energy deposition2) (caVg fuel) 0.318 0.323 0.320 0.311

Energy deposition 2

) (J/g fuel) 1.330 1.350 1.340 1.300

Energy deposition3) (per-unit) 0.985 1.000 0.991 0.963

Number of fissions x10"-4 (fiss) 1.860 1.880 1.950 2.040

Power of fuel rod') (kW) 4.200 4.260 4.420 4.610

Total Energy deposition2) (caVg fuel) 87.50 88.70 92.10 96.00

Energy deposition2) (J/g fuel) 366.0 371.0 386.0 402.0

1 Energy deposition3) (per-unit) 0.911 0.924 0.959 1.000

at time of3.65 s, 2) at infinite time, 3) Current value per maximum value

All numerical values or characteristics were calculated for length offuel stack

H-7
Individual Ch~i ____ ofRefabricated Fuel Rods:' '~

#M A14T Fe•l,ý[Pieu ý(F is nt -jadding) under iGR Tests.

Table H-1.4. Fuel Enthalpy Vs. Time Calculated by FRAP-T6 Code for Fuel Rod #H14T

Time Enthalpy at fuel radius Fuel e Energy deposition

_ fuel) __l/ in fuel rod

(S) 1.10mm 2.22 mm 2.89 mm 3.79 mm calg fuel J/g fuel cal/g fEel I Jigfuel

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3A

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5A

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

1.04

3.92

4.74

5.73

7.02

8.86

11.8

17.0

26.1

39.8

55.0

67.2

74.9

78.6

79.6

78.6

76.4

73.0

69.3

65.3

61.3

57.3

48.1

40.4

34.0

28.9

16.6

5.09

0.00

1.02

3.83

4.64

5.61

6.87

8.69

11.6

16.7

25.6

38.9

53.4

64.4

70.5

72.4

71.5

69.0

65.8

62.1

58.5

55.0

51.7

48.5

41.3

35.3

30.2

26.1

15.6

5.07

0.00

0.98

3.68

4.45

5.39

6.60

8.35

11.1

16.0

24.3

36.6

49.1

57.3

60.3

59.5

56.8

53.5

50.3

47.1

44.4

41.9

39.6

37.5

32.8

28.8

25.3

22.2

14.1

5.06

0.00

0.88

3.34

4.05

4.90

5.99

7.53

9.91

13.7

19.6

27.0

32.5

34.3

33.5

31.9

30.2

28.7

27.4

26.4

25.5

24.7

23.9

23.2

21.5

19.8

18.1

16.6

11.7

5.02

0.00

0.99

3.70

4.48

5.41

6.63

8.38

11.2

16.0

24.2

36.1

48.2

56.6

60.3

60.7

59.3

57.0

54.3

51.4

48.6

46.0

43.4

41.0

35.5

30.7

26.7

23.3

14.4

5.06

0.00

4.13

15.5

18.8

22.7

27.8

35.1

46.8

66.8

101

151

202

237

253

254

248

239

227

215

204

193

182

172

149

129

112

97.5

60.5

21.2

0.00

0.95

3.81

4.65

5.65

6.93

8.74

11.6

16.4

24.7

37.3

51.2

62.6

70.4

75.2

78.1

80.0

81.2

82.2

82.9

83.4

83.9

84.2

84.9

85.4

85.8

86.1

87.0

89.2

0.00

3.98

16.0

19.5

23.7

29.0

36.6

48.4

68.7

104

156

214

262

295

315

327

335

340

344

347

349

351

353

356

358

360

361

364

374

Radial enthalpy distribution and fuel enthalpy are presented at elevation 40.0 nMn

Mximum value of fuel enthalpy is 60.9 caVg fuel (t--4.33 s)

1 All numerical values are presented at elevation with peak po•-r

H-8
Iý eniiniVi~&stics of Refabdricagd Fuel Rods',''

.- . 4TI (Fresh.Q & e Cladding) winder IGR, esis -

Table H-1.5. Energy Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel

Rod #H14T

Energy Linear Energy of Clad-to-coolant heat

Time depositiont) poNeri) Fuel enthalpy') metal-water Leakage of energy transfer coefficient')

(s) (cal/g fuel) (kW/m) (cal/g fuel) reaction') (cal/g fuel) (kW/m2

K)

(cal/c fuel)

FRAP-T6 SCANAIR FRAP-T6 FRAP-T6 I SCANAIR FRAP-T6 SCANAMR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

1.08

4.33

5.28

6.42

7.87

9.92

13.1

18.6

28.1

42.3

58.1

71.2

80.0

85.5

88.8

90.9

92.3

93.4

94.1

94.8

95.3

95.7

96.5

97.1

97.5

97.8

98.8

101

0.00

3.72

7.59

8.82

10.9

14.5

21.5

35.2

61.8

* 103

137

129

93.8

59.7

36.1

22.2

14.5

10.2

7.52

5.93

4.86

4.09

3.35

2.28

1.66

1.27

1.04

0.66

0.08

0.00

0.99

3.70

4.48

5.41

6.63

8.38

11.2

16.0

24.2

36.1

48.2

56.6

60.3

60.7

59.3

57.0

54.3

51.4

48.6

46.0

43.4

41.0

35.5

30.7

26.7

23.3

14.4

5.06

0.00

0.97

3.82

4.53

5.54

6.85

8.45

11.4

16.6

24.1

36.7

49.4

57.2

60.8

60.9

59.2

57.1

54.3

51.6

48.8

46.0

43.8

41.4

35.9

31.4

27.3

23.8

14.9

5.14

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00-

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.01

0.01

0.02

0.02

0.03

0.09

0.55

1.60

3.63

7.09

11.8

17.2

22.5

27.6

32.2

36.4

40.4

43.9

47.1

50.1

52.9

59.0

64.1

68.4

72.0

81.8

93.8

0.00

0.00

0.03

0.04

0.05

0.07

0.09

0.14

0.70

1.68

3.83

7.53

12.2

17.8

22.6

27.9

32.1

36.5

40.3

44.0

47.5

50.2

53.2

59.6

64.8

69.4

73.3

83.4

96.1

0.00

0.03

0.03

0.03

0.03

0.03

0.03

0.74

2.23

4.21

7.29

10.6

12.8

13A

12.9

12.1

11.1

103

9.46

8.79

8.20

7.68

7.20

6.16

5.30

4.55

3.91

2.13

0.05

0.00

0.10

0.10

0.10

0.10

0.10

0.10

0.84

2.68

4.70

8.40

12.5

14.8

15.4

14.9

13.8

12.9

11.9

11.0

10.2

9.51

8.98

8.41

7.20

6.22

5.32

4.54

2.45

0.10 I I I I I A a. a. -

1) All numerical values are presented at elevation 'ith peak powr

H-9
i :4 d'vidij 4 ýoRefa'bricat'ed iFuel R vd" ..Fresh Fuel, zi ?tladdug ne Grsi

Table H-1.6. Temperature Variation, Fission Gas Release and ZrO2 Thickness Vs. Time for Fuel

Rod #H14T Calculated by FRAP-T6 and SCANAIR Codes .

Average

Time Fuel centerline Fuel surface Clad outer ZrO22)

(s) temperature1) temperature1 ) temperature1) thickness

(K) (K) (K) (4m)

FRAP-T6 SCANAIR FRAP-T6 SCANAIR FRAP-T6 SCANAIR FRApoT6

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

312

360

373

389

409

438

483

559

688

877

1080

1240

1339

1387

1400

1387

1358

1315

1267

1216

1163

l1ll

989

885

798

727

553

379

293

310

357

369

386

407

432

479

561

678

874

1082

1232

1330

1370

1380

1368

1337

1298

1250

1198

1152

1100

981

884

797

726

552

375

293

309

350

362

376

393

417

454

511

597

701

777

802

791

769

745

724

707

692

679

668

658

647

623

599

575

553

481

378

293

307

349

359

373

392

414

452

514

593

704

784

810

804

788

767

750

732

717

703

690

680

667

639

613

586

561

484

374

293

299

324

333

342

353

367

383

391

398

406

413

416

417

416

415

413

412

410

409

408

407

406

403

40i

399

397

391

376

293

298

322

329

338

350

362

379

384

387

393

398

401

401

401

400

399

397

396

395

394

394

393

391

390

389

387

383

370

)All numerical values arm presented at elevation with peak power

2) Initial Z0z thickness is 5 pin

H-10
#H14T rhFi e aWed Cladding) UnderIGR-Tek -ý I

Table H-1.7. Mechanical Characteristics of Fuel Rod NH14T Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes

Clad outer Fuel hoop Fuel - clad gap Clad hoop Clad hoop Internal gas Time temperature') straint) vidth1

) straint) stress1 ) pressure

(s) (K) (NO (mm) , (-U. (MPa) (MPa)

FRAPRT6 I A FRAFRT6 - I SCA FRAFAT6-TCANAN FRAFRT6I SCANAAI FR -T6 I S MAP4T6 [SCANAII

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

299

324

333

342

353

367

383

391

398

406

413

416

417

416

415

413

412

410

409

408

407

406

403

401

399

397

391

376

293

298

322

329

338

350

362

379

384

387

393

398

401

401

401

400

399

397

396

395

394

394

393

391

390

389

387

383

370

0.00 0.00 0.07 0.07 0.01 0.01 8.71.1 8.71 1.70

0.01 0.01 0.07 0.06 0.01 0.01 8.78 8.79 1.71

0.06

0.07

0.09

0.11

0.13

0.18

0.25

0.37

0.56

0.76

0.91

1.00

1.03

1.02

0.99

0.94

0.90

0.85

0.80

0.75

0.70

0.60

0.51

0.44

0.38

0.23

0.08

0.06

0.07

0.08

0.10

0.12

0.17

0.25

0.37

0.58

0.79

0.93

0.98

0.98

0.95

0.91

0.85

0.80

0.75

0.70

0.66

0.62

0.53

0.46

0.39

0.34

0.21

0.06

0.06

0.06

0.06

0.06

0.06

0.06

0.06

0.05

0.05

0.04

0.03

0.03

0.03

0.03

0.03

0.03

0.04

0.04

0.04

0.04

0.04

0.05

0.05

0.05

0.05

0.06

0.06

0.06

0.06

0.06

0.06

0.06

0.06

0.06

0.05

0.05

0.04

0.03

0.03

0.03

0.03

0.03

0.04

0.04

0.04

0.04

0.04

0.05

0.05

0.05

0.05

0.06

0.06

0.07

0.03

0.04

0.04

0.05

0.06

0.07

0.08

0.09

0.10

0.11

0.11

0.12

0.11

0.11

0.11

0.11

0.10

0.10

0.10

0.10

0.10

0.09

0.09

0.09

0.08

0.08

0.06

0.03

0.03

0.04

0.05

0.06

0.07

0.08

0.08

0.10

0.11

0.12

0.12

)0.12

0.11

0.11

0.11

0.10

0.10

0.10

0.10

0.10

0.09

0.09

0.09

0.08

0.08

0.06

8.96

9.00

9.05

9.10

9.18

9.28

9.42

9.61

9.81

9.96

10.1

10.1

10.1

10.1

10.1

10.1

10.1

10.0

10.0

9.98

9.95

9.87

9.79

9.72

9.65

9.43

9.07

9.00

9.04

9.10

9.18

9.26

9.43

9.72

10.1

10.6

11.2

11.5

11.6

11.5

11.4

11.3

11.2

11.1

11.0

10.9

10.8

10.7

10.5

10.4

10.2

10.1

9.64

9.06

1.75

1.75

1.76

1.77

1.79

1.81

1.83

1.87

1.90

1.93

1.95

1.96

1.96

1.96

1.96

1.95

1.95

1.94

1.94

1.93

1.93

1.91

1.90

1.88

1.87

1.83

1.77

1.70

1.72

1.75

1.76

1.77

1.78

1.80

1.82

1.85

1.89

1.94

1.99

2.01

2.02

2.02

2.02

2.01

2.01

2.00

1.99

1.98

1.97

1.97

1.95

1.93

1.91

1.90

1.85

1.77 L I .L .L .L _________ I I __________ I __________ I I

1) All numcrical values arc presented at clevation with peak pomwr

H-11
#H14T 'Jndivdu Ch'acTf Rcifabric'ait&I 'Fuel Ro'ds I (FreshFtiel.F Preý fdi'ng)under IGR.Tests,-'ý,-ý..ý

Table H-1.8. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #H14T

Axial interval Energy deposition at infinite time Fuel enthalpy

from-to at time (t=4.33 s)

(mm)-(mm) ca/g fuel Jg fuel per-unit cal/g fuel J/g fuel per-unit

33.0-47.1 103 433 1.00 60.9 255 1.00

47.1 -61.2 96.8 406 0.94 57.0 239 0.94

61.2-75.3 92.2 386 0.89 54.3 227 0.89

75.3 - 89.4 89.0 373 0.86 52.3 219 0.86

89.4- 103.5 87.5 366 0.85 51.4 216 0.85

103.5 - 117.6 86.9 364 0.84 51.1 214 0.84

117.6 - 131.7 87.6 367 0.85 51.5 216 0.85

131.7- 145.8 88.1 369 0.85 51.8 217 0.85

145.8- 159.9 88.9 372 0.86 52.3 219 0.86

159.9- 174.0 90.1 378 0.87 53.0 222 0.87

120

U

100

-80

- 60

40

0 20

U

• 2o

e0

20 40 60 80 100 120

Axial coordinate (mm)

140 160 180

Fig. H-1.4. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6 Code

for Fuel Rod #HI4T

H-12
#H14T (Fre~sh Fj,~ijdae CIa'ddin~g)uihder IG.?R esis;ýz2 ,

1.2

a,

~

0

0

p4

1.0

0.8

0.6

0.4

0.2

1 2 3 4

Radial fuel coordinate (mm)

80

70

60

50

040

0.

30

20

10

0

1.0 1.5 2.0 2.5 3.0 3.5

Radial fuel coordinate (mm)

4.0

Fig. H-1.5. Radial Distributions of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #H14T

H-13
#H14T Inidividuai ChGiatini0fRefabricated 'Fuel Rodsý:. :

I(Fresh Fuel Pre di~1C ding) under IGR Tests -

150

120

100

80

0

0

>1

90

60

60

4o2-

40~

20

0

30

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

1500

1200

20

E

F%

900

600

300

0

16 .

12

4 S

U

2

2

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. H-1.6. Energy and Temperature Characteristics Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes for Fuel Rod #H14T

H-14
#H14T I i !,(vi,~4~. fRfbi~e Fud R1s.:,. Fý ~dated Cadin~g, unýer]G-Ttsý

2.4

2.0

,1.6

2 1.2

E 0.8

0.4

0.0

0.14

0.12

0.10

0.08

0. 0.06

0.04

0.02

0.00

18

15

12

0

6

0

U

3

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

0.07

0.06

0.05

0.04 .

0.03 "g

0.02 :.

0.01

0.00

0 1 2 3 4 5 6 7 8 9 10

Time (s) -

Fig. H-1.7. Cladding Mechanical Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #H14T

H-15
MA1T I Jn'di'tid ' cht f Refabricatec Fu`l Rods-,

I(Fresh Fuel , Pre " a nejadding) under IGR 'Tests

1.5

1.2

F

0.9

ca

o 0.6

0.3

0.0

I -T6 1500

--- Fuel total hoop strain

-•3--- Fuel centerline temperature 1200

.. _.

300

600

"'le°

!4

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. H-1.8. Fuel Strain Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel Rod #1114T

H-16
#H14T I hdv ' ru -dristics- f kfabricýAt Fuel kods

;(Fresh F U 21-tdiated Claddi ig)uiider IGR.Tets

Table H-1.9. Some Results of PIE for Fuel Rod #H14T

Characteristic Value -, I.

l.

1.1.

1.2.

1.3.

1.4.

Measured parameters of cladding oxidation and cladding

deformation

Cladding thickness at elevation 85 mm for different azimuthal

angles (pim):

00

900

1800

2700

ZrO2 thickness at elevation 85 mm for different azimuthal angles

(Prm):

00

900

1800

2700

ctZr(O) thickness at elevation 85 mm for different azimuthal angles

(jim):

00

900

1800

2700

Clad hoop strain at elevation 85 mm (%)

705

700

691

695

5

5

5

5

0

0

0

0

0.5

2.

2.1.

2.2.

2.3.

2.4.

Measured parameters for FGR analysis

Internal gas composition (% by volume):

He

N2

02

Ar

C0 2

Kr

Xe

Free gas volume (cm3)

Gas pressure inside fuel rod under normal condition (MPa)

Kr concentration in fuel (cm3/1 fuel)

6.17

1.58

3. Measured parameters of cladding hydriding

3.1. Coefficient of hydride orientation (per-unit) 0.33

3.2. Hydrogen concentration (% by weight)

H-17
#H14T ,indi;idual Cliaiic't-'t~ic'"6Refabiicate~d Fuel I Rod6-I

[(Fre-sh-Fuel, Prir ____Caddirjiig)wder TcR Tests, i-.- 1

Table H-1.10. General Characteristic of Fuel Rod #H14T

Parameter Unit Value

Experiment FRAP-T6 SCANAIR

I Type of coolant -- water water water

2 Bumup MWd/kg U 0 0 0

3 Energy deposition in fuel rod cal/g fuel 91 91 91

4 Peak fuel enthalpy cal/g fuel - 61 61

5 Peak fuel temperature K - 1400 1380

6 Peak clad temperature K - 417 401

7 Fuel rod failure Yes, No No No

8 Type of failure:

- cladding rupture due to ballooning Yes, No No No

- cladding rupture due to PCMI Yes, No No No

- fragmentation of fuel rod Yes, No No -

9 Failure time s -

10 Fuel cnthalpy at failure cal/g fuel - -

•11 Outer cladding temperature at failure K - -

12 Internal gas pressure at failure MPa -

13 ZrO2 thickness after test Pm 5 5

14 Residual clad hoop strain:

- peak value for ballooning area % -

- other location % 0.5 0 0

"Calculated values by FRAP-T6 and SCANAIR codes are average along height or fuel rod excluding ballooning region

H-I8
H-19
#H15T individuail hirAn"M1wlf 6ariae Fue~l Rods

(Fresh Fuel, Piefpaji _diCladding) underiGR-Tests

1

2,

Fig. H-2.1. Appearance of Fuel Rod #Hl5T (photographs and X-ray photograph)

H-20
#H15T I IndivdUflfiT edstics of Refabricated Fue'l Rod'

Ffre~th" %ýiraiated Claddingk)'uderJOR Tests'",

Position I

Position2

Fig. H-2.2. Cross-Section and Cladding Microstructure for Fuel Rod #H15T at 117 mm Elevation

H-21
#H15T [ •Individual "6 fRefabricated Fuel Pods

i(FreshFiel m'a"l'.iadding) under IGR-Tests-i,'

Position2

Position3

Fig. H-2.3. Fuel Microstructure for Fuel Rod #H15T at 117 mm Elevation

H-22
#H15T Ininividual C~jacteristics of Refabricated Fuel Rods'

I (Fresh FuelTj"irradiated Cladding) under IGR Tests',`

Table 11-2.1. Time Dependent Energy Characteristics of Fuel Rod #t115T

Reactor Cumulative number of fissions Power of Energy deposition

Time energy in fuel rod (fiss) fuel rod in fuel rod

(s) deposi- U235 U238 Total (kW) cal/g fuel J/g fuel lion) 1l~4 1l-2 X10-14

N(1 0 1 0)

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

9.0

10.0

20.0

30.0

0o

0.000

1.040

6.470

9.380

14.50

23.60

37.80

53.60

66.30

75.10

81.10

85.10

87.90

89.90

91.40

92.50

93.30

94.00

94.60

95.00

95.40

95.70

95.90

96.50

96.80

97.10

97.30

97.70

98.00

99.20

99.60

100.0

0.000

0.245

1.520

2.202

3.408

5.557

8.913

12.58

15.55

17.65

19.05

20.01

20.71

21.15

21.50

21.76

21.93

22.11

22.19

22.37

22.46

22.46

22.54

22.72

22.81

22.81

22.89

22.98

23.07

23.33

23.42

23.59

0.000

0.087

0.542

0.786

1.215

1.975

3.163

4.483

5.549

6.291

6.790

7.122

7.358

7.524

7.646

7.742

7.812

7.873

7.917

7.952

7.987

8.013

8.030

8.074

8.100

8.126

8.144

8.179

8.205

8.301

8.336

8.406

0.000

0.246

1.529

2.211

3.417

5.575

8.913

12.67

15.64

17.74

19.14

20.10

20.71

21.23

21.58

21.85

22.02

22.19

22.28

22.46

22.54

22.54

22.63

22.72

22.81

22.89

22.98

23.07

23.16

23.42

23.5i

23.68

0.000

1.660

7.480

12.41

22.46

39.06

53.13

48.67

35.48

24.12

16.25

11.18

7.934

5.785

4.352

3.355

2.656

2.150

1.774

1.485

1.250

1.066

0.918

0.660

0.504

0.407

0.343

0.292

0.233

0.060

0.031

0.000

0.000

2.779

17.30

25.08

38.71

63.18

101.4

143.3

177.4

201.0

216.7

228.1

235.9

241.2

244.7

248.2

250.8

252.5

254.3

255.2

256.0

257.8

257.8

259.5

261.3

262.1

262.1

263.9

264.8

269.1

270.9

277.0

0.000

11.62

72.44

104.9

161.7

264.8

424.7

600.3

742.7

841.5

907.0

955.1

987.4

1009.

1024.

1039.

1049.

1057.

1064.

1068.

1071.

1079.

1079.

1086.

1094.

1098.

1098.

1105.

1108.

1126.

1134.

1160.

Maximum value ofpo~er is 53.8 kW (t = 2.85 s)

I) Current energy deposition per maximum energy deposition (at infinite time)

H-23
#H15T I lndividual Clharactezistics 6fRefabricated Fuel Rods

(Fresh Fuel, Preirraitc-d Cladding) under IGR Tests

Table 11-2.2. Axial Energy Characteristics of Fuel Rod #1115T

Axial Cumulative number of fissions Maximum Energy deposition

coordinate at axial interval (fiss) power of at infinite time*

from lower U23 5 U238 Total fuel rod cal/g fuel Jig fuel per-unit)

end of fuel xl0"3 x10.1 x×10. 3 (kW)

rod t=2.85s I

(mm)

20.0

25.01)

30.0

35.0

40.0

45.0

50.0

55.0

60.0

65.0

70.0

75.0

80.0

85.0

90.0

95.0

100.0

105.0

110.0

115.0

120.0

125.0

130.0

135.0

140.0

145.0

150.0

155.0

160.0

165.0

170.02)

175.0

0.000

3.530

9.612

9.350

9.088

8.826

8.686

8.581

8.389

8.284

8.205

8.109

8.057

8.004

7.960

7.952

7.899

7.899

7.960

8.013

8.004

7.934

7.960

8.109

8.118

8.153

8.205

8.231

8.310

8.327

0.332

0.000

0.000

1.031

2.866

2.884

2.875

2.892

2.919

2.954

2.954

2.971

2.988

3.006

3.023

3.041

3.050

3.058

3.041

3.050

3.058

3.076

3.050

2.997

2.980

2.988

2.962

2.927

2.884

2.84b

2.805

2.744

0.107

0.000

0.000

3.539

9.699

9.437

9.088

8.913

8.712

8.616

8.415

8.319

8.240

8.135

8.083

8.030

7.995

7.978

7.926

7.926

7.995

8.048

8.030

7.969

7.995

8.135

8.144

8.188

8.240

8.266

8.336

8.354

0.333

0.000

0.000

0.804

2.193

2.141

2.062

2.019

1.984

1.957

1.914

1.887

1.870

1.852

1.835

1.826

1.818

1.818

1.800

1.800

1.818

1.826

1.826

1.809

1.818

1.852

1.852

1.861

1.870

1.879

1.896

1.896

0.076

0.000

0.000

323.3

318.1

309.3

300.6

294.5

289.2

284.9

278.7

275.3

272.6

270.0

268.3

266.5

264.8

264.8

264.8

264.8

264.8

265.6

266.5

267.4

268.3

270.0

270.9

271.8

273.5

273.5

276.1

274.4

275.3

0.000

0.000

1354.

1332.

1295.

1258.

1233.

1211.

1193.

1167.

1153.

1141.

1130.

1123.

1116.

1108.

1108.

1108.

1108.

1108.

1112.

1116.

1119.

1123.

1130.

1134.

1138.

1145.

1145.

1156.

1148.

1153.

0.000

0.00

1.00

0.98

0.96

0.93

0.91

0.89

0.88

0.86

0.85

0.84

0.84

0.83

0.82

0.82

0.82

0.82

0.82

0.82

0.82

0.82

0.83

0.83

0.84

0.84

0.84

0.85

0.85

0.85

0.85

0.85

0.00 A. L L .5. L A.

All numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate ± 2.5 mm

) Initial coordinate of fuel is 25.7 mm

2) End coordinate of fuel is 167.7 mm

3) Current value per maximum value

H-24
#H15T Inldividual Characteristics of Refabricated Fuel Rods' -

I(Fresh Fuel••eirradiated Cladding) under IGR Tei.ts_

Table 11-2.3. Radial Energy Characteristics of Fuel Rod #H15T

Coordinates of fuel zones (mm)

Characteristics* I zone 2 zone 3 zone 4 zone

1.10 -2.12 2.12 -2.79 2.79-3.32 3.32-3.79

Number of fissions x10"'4 (fiss) 5.671 5.750 5.968 6.222

Power of fuel rod) (kW) 12.93 13.02 13.54 14.16

U233 Energy deposition2) (ca/g fuel) 264.8 268.3 278.7 291.0

Energy deposition2) (J/g fuel) 1108 1123 1167 1218

Energy deposition3) (per-unit) 0.91 0.922 0.958 1.000

Number of fissions x 10-12 (fiss) 2.106 2.132 2.115 2.053

Power of fuel rod') (kW) 0.047 0.048 0.047 0.046

U238 Energy deposition 2) (cal/g fuel) 0.970 0.987 0.970 0.944

Energy deposition2) (J/g fuel) 4.063 4.133 4.063 3.950

Energy deposition3) (per-unit) 0.982 1.000 0.982 0.956

Number of fissions x 10"14 (fiss) 5.697 5.767 5.986 6.248

Power of fuel rod1) (kW) 12.93 13.11 13.63 14.16

Total Energy deposition 2

) (calg fuel) 265.6 269.1 279.6 291.9

Energy deposition 2) (J/g fuel) 1112 1126 1171 1222

I Energy deposition 3) (per-unit) 0.910 0.922 0.958 1.000

I) at time of 2.85 s, 2) at infinite time, Current value per maximum value

All numerical values of characteristics were calculated fur length or fuel stack

H-25
#H15T Individ(al C haPrciac d oflRefabricatn dFuel Rods.

S(Fresh Fuel; Preinrad,'ted Cladding) under IGR Tests

Table 11-2.4. Fuel Enthalpy Vs. Time Calculated by FRAP-T6 Code for Fuel Rod #1115T

Time Enthalpy at fuel radius Fuel e f J Energy deposition

()ime(cal fuel) F in fuel rod

(s) 1.10 un 2.22mm I 2.89 mm I 3.79_ m ca/guel J/gfuel calgfuel I Jgfuel

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

3.03

18.3

26.6

41.4

68.2

110

157

194

219

235

244

249

250

250

249

247

244

242

238

235

231

227

217

206

193

179

124

13.8

0.00

2.99

17.9

26.1

40.5

66.8

108

152

187

207

219

225

227

228

228

226

224

222

219

215

212

208

204

194

181

167

153

110

13.6

0.00

2.88

17.1

24.7

38.2

62.5

99.4

136

158

171

180

187

191

192

192

190

188

185

183

180

176

173

170

158

144

132

122

93.3

13.2

0.00

2.57

14.6

20.2

28.9

41.1

48.5

45.5

66.6

95.8

119

126

129

129

129

129

128

126

125

123

122

120

116

101

94.0

88.8

84.4

70.7

12.4

0.00

2.86

17.0

24.4

37.4

60.3

93.4

124

149

168

182

190

193

195

194

193

191

189

186

183

180

177

174

161

149

138

128

96.3

13.3

.0.00

12.0

71.1

102

157

253

391

521

626

703

763

795

810

815

814

808

800

790

780

768

755

742

727

677

626

580

538

.403

55.5

0.00

2.77"

17.2

25.0

38.6

62.9

101

143

177

200

216

227

235

241

245

248

250

252

254

255

257

258

258

260

261

262

263

265

271

0.00

11.6

72.2

105

162

264

422

598

740

840

907

953

985

1008

1025

1039

1049

1058

1064

1070

1075

1079

1083

1089

1094

1098

1101'

1111

1138

Radial enthalpy distribution and fuel enthalpy are presented at elevation 32.8 mm

Maximum value of fuel enthalpy is 194.6 ca/g fuel (t--4.24 s)

1) All numerical values are presented at elevation %%ith peak po%%cr

H-26
#H15T Indivi•ual Chlaracteristics of Refabricated Fuel Rods

(Fresh Fuerji.Irradiated Cladding) Under IGR Tests:

Table 11-2.5. Energy Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel

Rod #1I15T

Energy Linear Energy of Clad-to-coolant heat

Time e ) Fuel enthalpy1 ) metal-Water Leakage of energye) transfer coefficienti)

(s) deposition power (caVg fuel) reactiont) (cal/g fuel) (calfg fuel) (kW/m) fuel) ___mK) ( /(calla 

FRAP-T6 SCANAIR FRAP-T6 FRAP-T6 SCANAIR FRAP-T6 SCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

3.11

19.3

28.0

43.3

70.6

113

160

198

225

243

255

264

270

274

278

281

283

285

286

288

289

290

291

293

294

295

297

304

0.00

13.1

59.2

98.1

177

309

420

385

281

191

129

88.6

62.8

45.8

34.5

26.6

21.0

17.0

14.3

11.9

10.0

8.57

7.37

5.28

4.03

3.25

2.73

1.86

0.25

0.00

2.86

17.0

24.4

37.4

60.3

93.4

124

149

168

182

190

193

195

194

193

191

189

186

183

180

177

174

161

149

138

128

96.3

13.3

0.00

3.15

19.4

26.8

41.8

69.0

102

141

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00 -

0.02

0.06

0.13

0.22

0.33

0.45

0.56

0.66

0.75

0.83

0.90

0.95

0.97

0.97

0.97

0.97

0.97

0.97

0.97

0.00

0.00

0.35

1.37

3.29

7.10

15.3

26.5

29.1

33.1

37.5

41.9

46.4

51.1

55.9

60.8

65.8

70.7

75.1

80.0

84.8

91.2

103

134

148

161

172

209

304

0.00

0.01

0.90

2.15

4.70

9.81

18.6

26.5

0.00

0.03

2.20

4.07

0.00

0.10

3.49

5.50

9.77

18.6

31.7

1.30

7.14

13.4

25.7

3.96

1.29

1.39

1.38

1.39

1.41

1.42

1.43

1.44

1.44

1.43

1.43

1.43

1.42

2.89

6.31

14.5

12.8

11.6

10.7

7.95

0.67

1) All numerical values are presented at elevation with peak poswr

H-27
#H15T individd'' Charamteiristics of Refabricated Fuel Rods'

I (Freslh Fuel, Preiniaý1ted Cladding) utnder IGR Tests

Table H-2.6. Temperature Variation, Fission Gas Release and ZrO2 Thickness Vs. Time for Fuel

Rod #MU5T Calculated by FRAP-T6 and SCANAIR Codes

Average

Time Fuel centerline Fuel surface ' Clad outer ZrO2a2)

(S) temperature 1) temperature°) temperature 1) thickness (K) (K) (K)

_ _ I(PTm) I SF ISF 

FRAP-T6 SCANAIR FRAP-T6 SCANAIR FRAP-T6 jSCANAIPR FRAP-T6

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

•4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

345

578

696

899

1253

1778

2286

2613

2799

2905

2962

2990

3000

3000

2992

2979

2963

2947

2926

2903

2879

2853

2783

2705

2609

2494

1943

512

293

343

590

698

907

1279

1744

2286

293

*338

524

605

727

895

994

954

1233

1603

1880

1961

1992

2002

2000

1992

1980

1966

1951

1934

1915

1889

1850

1669

1581

1516

1461

1286

492

293

342

558

642

793

1006

1135.

1272

293

307

391

398

406

417

433

666

1083

1237

1221

1234

1257

1278

1292

1299

1301

1299

1293

1285

1275

1190

1009

419

416

414

413

407

383

293

307

385

389

395

405

416

894

5.00

5.00

5.00

.5.00

5.00

5.00

5.00

5.00

5.00

5.03

5.07

5.10

5.15

5.21

5.27

5.35

5.43

5.50

5.56

5.63

5.68

5.72

5.73

5.73

5.73

5.73

5.73

5.73

5.73

All numerical values are presented at elevation with peak power

2 Initial ZrO2 thickness is 5 pm

H-28
#H15T Individual Characteristics of Refabricated Fuel Rods.

(Frihý FulIrizmdiated Cladding) under IGR Tests

Table 11-2.7. Mechanical Characteristics of Fuel Rod #H15T Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes

Clad outer Fuel hoop Fuel - clad gap Clad hoop Clad hoop Internal gas Time temperature') strain') width') straini) stressi) pressure

(s) (K) (%) (mm) '(j%) J (MPa) (MPa)

FRAP-T6 I SCAAANAR- FAN-T6 SCAN T6SCCANAIR SAAPRT6TSCANA FRAP-T6 ISCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5A

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

307

391

398

406

417

433

666

1083

1237

1221

1234

1257

1278

1292

1299

1301

1299

1293

1285

1275

1190

1009

419

416

414

413

407

383

293

307

385

389

395

405

416

894

0.00

0.00

0.20

0.32

0.53

0.92

1.57

2.24

2.72

3.04

3.24

3.35

3.41

3.43

3.42

3.40

3.38

3.34

3.31

3.27

3.22

3.17

3.12

2.95

2.77

2.59

2.40

1.69

0.13

0.00

0.04

0.23

0.32

0.51

0.91

1.46

2.13

0.07

0.07

0.07

0.06

0.05

0.04

0.02

0.00

0.00

0.09

0.37

0.37

0.37

0.37

0.37

0.37

0.37

0.37

0.37

0.37

0.37

0.37

0.38

0.38

0.39

0.40

0.40

0.43

0.49

0.07 1 0.01

0.07

0.06.

0.06

0.05

0.04

0.02

0.01

0.02

0.08

0.09

0.10

0.12

0.15

0.36

0.76

3.01

10.4

10.4

10.4

10.4

10.5

10.5

10.5

10.5

10.5

10.5

10.4

10.4

10.6

10.2

10.2

10.2

10.2

10.2

10.2

0.01

0.02

0.09

0.09

0.11

0.13

0.18

0.50

8.71

8.88

9.39

9.55

9.75

10.0

10.3

111

45.3

11.3

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

8.68

8.90

9.70

9.99

10.5

11.5

12.8

11.2

1.70

1.73

1.83

1.85

1.89

1.94

1.99

2.03

2.04

2.04

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

1.70

1.73

1.84

1.86

1.90

1.94

1.96

1.99

I" All numerical values are prcsentcd at elevation Wth pcak po1cr

H-29
I#H15T Individual Characteristics of Refabricated Fuel Rods S(Fresh Fu-l, Preirradiated Cladding) undeIGR Tests ' ,

Table H-2.8. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #1115T

Axial interval Energy deposition at infinite time Fuel enthalpy

from-to at time (t=4.24 s)

(mm)-(mm) caVg fuel Jig fuel per-unit cal/g fuel J/g fuel per-unit

25.7-39.9 311 1301 1.00 195 816 1.00

39.9-54.1 290 1214 0.93 182 761 0.93

54.1-68.3 277 1160 0.89 174 727 0.89

68.3 - 82.5 271 1135 0.87 170 711 0.87

82.5-96.7 266 1114 0.86 167 698 0.86

96.7- 110.9 266 1114 0.86 167 698 0.86

110.9 - 125.1 269 1127 0.87 169 707 0.87

125.1 - 139.3 272 1139 0.88 170 714 0.88

139.3 - 153.5 275 1150 0.88 172 721 0.88

153.5 - 167.7 276 1156 0.89 173 724 0.89

350

300

250

5 200

• 150

o

° 0 50 Energy deposition

Fuel enthalpv

20 40 60 80 100 120

Axial coordinate (mm) -

140 160 180

Fig. 11-2.4. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6 Code

for Fuel Rod #H15T

H-30
#H15T Idividual Chiar'ctcristics of Refabricated Fuel Rods (Fresh• Fuel:eiradiated Cladding) under IGR Tests

1.2

J,

0

1.0 -

0.8 -

0.6 -

0.4 -

I U

I

*.1

~2~~~.

II IV

(1

0.2 ~1~ .4-. a

2

i

1 3 4

Radial fuel coordinate (mm)

300

250

-- 200

w CE 150

r.u 100

50

0

1.0 1.5 2.0 2.5 3.0

Radial fuel coordinate (mm)

3.5 4.0

Fig. H-2.5. Radial Distributions of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #H15T

H-31
#H15T Individual Characteristics of Refabricated Fuel Rods

.(Fresh Fuel, Preirradiated Cladding) under IGR Tests -

500

400

,- 300

200

100

0

3500

3000

2500

o 2000

1500

1000

500

0

300

C0 1 2 3 4 5 6 7 8 9 10

Time (s)

35

30

25

20 2

C

15. C

0

10 6

U

5

2

2

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. 11-2.6. Energy and Temperature Characteristics Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes for Fuel Rod #H15T

H-32
#H15T individuAl Chbcterisýis'of Refabricated Fuel RodsiinrR '

I (Fresh Fuilfctrradiated Cladding) under IGR Tests

2.5

2.0

.2 1.5

- '.o1.0

E

0.5

0.0

150

120

90

0

0 60 =

30

0

I

0 1 2 3 4 5 6 7 8 9 10

Time (s)

15

12

N.

T

9

6

3

0.5

0.4

E

E

0.3 -

0.2 Co

0.1

0.0

-:$...

FRAP-T6

.... SCANAIR

+ Clad hoop strain

- - Fuel-clad gap iidth i' i I

0* I I

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. H-2.7. Cladding Mechanical Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #HI5T

H-33
:Indiviual Characterjstics of Refabricated Fuel Rods #H15T (Fiesh Fuel, Preirradlated Cladding) under IGR Tests

3.5

3.0

2.5

", 2.0

1.5

1.0

0.5

0.0

3500

3000

2500

2000

1500

1000

500

0

2

U

0.

E

U

U

U

U

U

U

~L.

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. 11-2.8. Fuel Strain Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel Rod #1115T

H-34
#H15T JIdiv'idual Characteristics of Refabricated Fue¢l Rods

(Fresh Fuel, Preirradiated Cladding) under IGR Tests -7

Table 11-2.9. Some Results of PIE for Fuel Rod #1115T

Characteristic Value - +

I.

1.1.

1.2.

1.3.

1.4.

Measured parameters of cladding oxidation and cladding

deformation

Cladding thickness at elevation 117 mm for different azimuthal

angles (pm):

00

900

1800

2700

ZrO2 thickness at elevation 117 mm for different azimuthal angles

(pm):

00

900

1800

2700

aZr(O) thickness at elevation 117 mm for different azimuthal

angles (gm):

00

900

1800

2700

Clad hoop strain at elevation 117 mm (%)

700

R

600

600

5

5

5

5

0

0

0

0

9.6 A

2.

2.1.

Measured parameters for FGR analysis

Internal gas composition (% by volume):

He

N2

02

Ar

CO2

Kr

Xe

Free gas volume (cm3

)

Gas pressure inside fuel rod under normal condition (MPa)

Kr concentration in fuel (cm3

/• fuel)

2.2.

2.3.

2A.4

3. Measured parameters of cladding hydriding

3.1. Coefficient of hydride orientation (per-unit)

3.2. Hydrogen concentration (% by weight)

H-35
#H15T JndividualChaac*ter'istics of Refabricated Fuel Rods

(Fresh Fuel, Preiriaaatd Cladding) Under IGR Tests i

Table 11-2.10. General Characteristic of Fuel Rod #H15T

Parameter Unit Value

Experiment FRAP-T6 SCANAIR

I Type of coolant -- water water water

2 Burnup MWd/kg U 0 0 0

3 Energy deposition in fuel rod cal/g fuel 277 277 277

4 Peak fuel enthalpy cal/g fuel - 195 -

5 Peak fuel temperature K - 3001 -

6 Peak clad temperature K - 1301 -

7 Fuel rod failure Yes, No Yes Yes -

8 Type of failure:

- cladding rupture due to ballooning Yes, No Yes Yes

- cladding rupture due to PCMI Yes, No No No

- fragmentation of fuel rod Yes, No No - -

9 Failure time s - 3.49

10 Fuel enthalpy at failure cal/g fuel - 175

11 Outer cladding temperature at failure K - 1230

12 Internal gas pressure at failure MPa - 2.04

13 ZrO2 thickness after test gtm 5.0 5.73

14 Residual clad hoop strain:

- peak value for ballooning area % 9.6 10.13

- other location'% - 0.45

"Calculated values by FRAP-T6 and SCANAIR codes are average along height of fuel rod excluding ballooning region

H-36
4

APPENDIX"1

Ituiviididal: Characteristic's .:1 jor he! '

rJ6 T uger1 J•R4"es

rMP-i 'er-.IGR;-est -- 

H-37
#H16T IF•shiv'it4ieChr la d d ing riu ated e';fe F.el .- ids'

[ (Fre-sh Fuel. PritiiiTdlid.C ladding) under IGR Tet

Positionlrn

C

Axial coordinatc (mm)

Fig. 1H-3.1. Appearance of Fuel Rod #NI16T (photographs and X-ray photograph) and Profilometry

H-38
#H16T I d ( 6f Refabricated Fuel Rod~s -

(Fres Fu~~ rn ClatdCidding) iuinde'rIGR*rTes-ts I,ý

rI-1

Position 1

Position 1

Fig. 11-3.2. Cross-Section and Cladding Microstructure for Fuel Rod #1116T at 95 mm Elevation

H-39
#H16T I Tndivid~iai Cha~ct~~il~ofRefabuicated Fuel Rods

(Fresh Fuel, Preirr~i~t~WCladdin~) under IGR ,Tests '

Position 1

Position2

Fig. 11-3.3. Fuel Microstructure for Fuel Rod #H16T at 95 mm Elevation

H-40
#H16T IIndividua 6istkcs of Refabnicated Fuel Rods "

.(Fr-sFuq natedCladding)uinder IGR Tests.

Table 11-3.1. Time Dependent Energy Characteristics of Fuel Rod #1116T

Reactor Cumulative number of fissions Power of Energy deposition

Time energy in fuel rod (fiss) fuel rod in fuel rod

(s) deposi- u 3 U2 Total (kW) calg fuel J/g fuel

tin__10_14) x 100 12 x10"14

N%

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

9.0

10.0

20.0

30.0

00

0.000

0.473

1.890

2.290

2.730

3.200

3.710

4.260

4.850

5.470

6.130

6.860

7.710

8.790

10.30

12.80

17.20

25.10

37.60

53.20

67.40

77.10

82.80

89.00

91.70

93.30

94.40

95.90

96.80

98.70

99.10

100.0

0.000

0.078

0.313

0.378

0.450

0.529

0.613

0.704

0.801

0.904

1.010

1.130

1.270

1.450

1.710

2.120

2.840

4.140

6.210

8.780

11.10

12.70

13.70

14.70

15.10

15.40

15.60

.15.80

16.00

16.30

16.40

16.50

0.000

0.028

0.112

0.135

0.161

0.189

0.219

0.252

0.286

0.323

0.362

0.405

0.455

0.519

0.610

0.757

1.020

1.480

2.220

3.140

3.980

4.550

4.890

5.260

5.410

5.510

5.580

5.660

5.710

5.830

5.860

5.910

0.000

0.078

0.314

0.380

0.452

0.530

0.615

0.706

0.803

0.907

1.020

1.140

1.280

1.460

1.710

2.120

2.850

4.160

6.230

8.820

11.20

12.80

13.7o

14.80

15.20

15.50

15.60

15.90

16.00

16.40

16.40

16.60

0.000

0.441

0.884

0.972

1.060

1.150

1.240

1.330

1.420

1.510

1.610

1.810

2.190

2.930

4.420

7.500

13.60

23.60

34.10

36.80

28.30

17.40

10.10

3.470

1.960

1.350

0.898

0.611

0.336

0.053

0.025

0.000

0.000

0.895

3.580

4.340

5.160

6.060

7.030

8.070

9.180

10.40

11.60

13.00

14.60

16.70

19.60

24.30

32.60

47.50

71.10

101.0

128.0

146.0

157.0

169.0

174.0

177.0

180.0

183.0

185.0

189.0

191.0

195.0

0.000

3.750

15.00

18.20

21.60

25.40

29.40

33.80

38.40

43.50

48.60

54.40

61.10

69.90

82.00

102.0

136.0

199.0

298.0

423.0

536.0

611.0

657.0

707.0

728.0

741.0

753.0

766.0

774.0

791.0

800.0

816.0

Maximum value of power is 37.3 kW (t = 5.35 s)

1) Current energy deposition per maximum energy deposition (at infinite time)

H-41
#H16T SIndividual Chara• FE ZIof Refabricated Fuel Rods

l(ffsh Fuel; PreiriMdatdladdifj)'tifidei IGR'Tists x :

Table H-3.2. Axial Energy Characteristics of Fuel Rod #H16T

Axial Cumulative number of fissions Maximum Energy deposition

coordinate at axial interval (fiss) power of at infinite time*

from lower u235 u238 Total fuel rod ca/g fuel Jig fuel per-unit3)

end of fuel x10." X10-1 x1o13 (kW)

rod t=5.35s s

(mm) -

20.0

25.0')

30.0

35.0

40.0

45.0

50.0

55.0

60.0

65.0

70.0

75.0

80.0

85.0

90.0

95.0

100.0

105.0

110.0

115.0

120.0

125.0

130.0

135.0

140.0

145.0

150.0

155.0

160.0

165.02)

170.0

0.000

2.270

6.560

6.410

6.270

6.120

6.020

5.930

5.890

5.860

5.780

5.710

5.670

5.640

5.640

5.640

5.710

5.710

5.680

5.710

5.720

5.750

5.780

5.750

5.780

5.780

5.800

5.820

5.760

5.000

0.000

0.000

0.678

2.000

2.020

2.040

2.050

2.070

2.080

2.110

2.140

2.150

2.140

2.150

2.160

2.170

2.170

2.200

2.200

2.180

2.170

2.160

2.150

2.140

2.100

2.080

2.040

2.010

1.970

1.910

1.620

0.000

0.000

2.280

6.580

6.430

6.290

6.140

6.040

5.950

5.910

5.880

5.800

5.730

5.690

5.670

5.660

5.660

5.730

5.730

5.700

5.730

5.740

5.770

5.800

5.780

5.800

5.800

5.820

5.840

5.780

5.020

0.000

0.000

0.512

1.480

1.440

1.410

1.380

1.360

1.340

1.330

1.320

1.300

1.290

1.280

1.270

1.270

1.270

1.290

1.290

1.280

1.290

1.290

1.300

1.300

1.300

1.300

1.300

1.310

1.310

1.300

1.130

0.000

0.000

223.0

219.0

214.0

210.0

205.0

201.0

198.0

196.0

194.0

191.0

189.0

188.0

188.0

188.0

187.0

188.0

188.0

188.0

189.0

189.0

190.0

192.0

192.0

193.0

193.0

194.0

195.0

196.0

196.0

0.000

0.000

933.0

917.0

896.0

879.0

858.0

841.0

829.0

820.0

812.0

800.0

791.0

787.0

787.0

787.0

783.0

787.0

787.0

787.0

791.0

791.0

795.0

804.0

804.0

808.0

808.0

812.0

816.0

820.0

820.0

0.000

0.00

1.00

0.98

0.96

0.94

0.92

0.90

0.89

0.88

0.87

0.86

0.85

0.84

0.84

0.84

0.84

0.84

0.84

0.84

0.85

0.85

0.85

0.86

0.86

0.87

0.87

0.87

0.87

0.88

0.88

0.00

All numerical values of characteristics arm presented as average values at the length interval equal to the axial coordinate ±2.5mm

!) Initial coordinate of fuel is 25.8 mm

2) End coordinate of fuel is 166.8 mm

3) Current value per maximum value

H-42
#H16T I "ndividualj-T-Lctedistics of Refabricated Fuel Rods'.

,(Fresh Fel•0 ?radiated Cladding) undei IGR Tests

Table H-3.3. Radial Energy Characteristics of Fuel Rod #H16T

Coordinates of fuel zones (mm)

Characteristics* I zone 2 zone 3 zone 4 zone

1.10-2.12 2.12-2.79 2.79-3.32 3.32-3.79

Number of fissions x 10"14 (fiss) 3.970 4.020 4.170 4.350

Power of fuel rod1 ) (kW) 8.920 9.040 9.390 9.790

U235 Energy deposition 2

) (callg fuel) 187.0 189.0 197.0 205.0

Energy deposition2) (J/g fuel) 783.0 791.0 825.0 858.0

Energy deposition3) (per-unit) 0.912 0.922 0.961 1.000

Number of fissions x 10-12 (fiss) 1.480 1.500 1.490 1.440

Power of fuel rod') (kW) 0.033 0.033 0.033 0.032

U238 Energy deposition2 ) (caVg fuel) 0.686 0.697 0.690 0.671

Energy deposition2 ) (J/g fuel) 2.870 2.920 2.890 2.810

Energy deposition3) (per-unit) 0.984 1.000 0.990 0.963

Number of fissions x10" (fiss) 3.980 4.030 4.190 4.370

Power of fuel rod') (kW) 8.950 9.070 9.420 9.820

Total Energy deposition2 ) (callg fuel) 187.0 190.0 197.0 206.0

Energy deposition2 ) (J/g fuel) 783.0 795.0 825.0 862.0

Energy deposition3) (per-unit) 0.908 0.922 0.956 1.000

)ttime or 5.35 s. 2) at infinite time. 3) Current value per maximum v alue

* All numerical values ofcharacteristics were calculated for length offuel stack

H-43
#H16T Individual Chainto&I~s of Refabricated Fuel Rods

(Fresh Fuel, Preiimr; t&Cladding) .. under IGR Tests

Table H-3.4. Fuel Enthalpy Vs. Time Calculated by FRAP-T6 Code for Fuel Rod #1116T

Enthalpy at fuel radius Fe Energy deposition

Time (cal/& fuel) Fuel in fuel rod

(S) 1.10mm I 2.22 mm 2.89mm I3.79_ m calfg fuel Jig fuel calg fuel Jig fuel

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

0.96

3.63

4.35

5.14

5.99

6.90

7.88

8.92

10.0

11.2

12.5

13.9

15.9

18.7

23.4

32.0

47.7

73.0

105

133

152

163

168

159

142

123

63.7

5.70

0.00

0.95

3.56

4.27

5.04

5.88

6.77

7.73

8.74

9.82

11.0

12.2

13.6

15.5

18.2

22.8

31.2

46.6

71.3

102

129

146

152

145

129

111

96.2

54.2

5.67

0.00

0.92

3.44

4.12

4.87

5.67

6.54

7.46

8.44

9.47

10.6

11.7

13.0

14.7

17.3

21.5

29.4

43.9

66.7

93.9

115

123

121

103

86.7

73.9

65.5

42.6

5.62

0.00

0.84

3.17

3.80

4.49

5.23

6.03

6.88

7.78

8.73

9.66

10.6

11.6

13.0

15.0

18.2

24.0

33.5

45.3

53.1

51.9

49.9

46.9

39.6

34.8

33.1

32.5

27.8

5.51

0.00

0.92

3.45

4.14

4.89

5.70

6.57

7.49

8.48

9.52

10.6

11.8

13.1

14.8

17.3

21.6

29.4

43.4

65.4

90.8

110

120

121'

112

99.8

87.2

77.1

46.4

5.62

0.00

3.85

14.5

17.4

20.5

23.9

27.5

31.4

35.5

39.9

44.4

49.3

54.8

62.0

72.6

90.4

123

182

274

380

462

501

509

470

418

366

323

194

23.6

0.00

0.89

3.58

4.33

5.16

6.06

7.03

8.07

9.18

10A

11.6

13.0

14.6

16.7

19.6

243

32.6

47.5

71.1

101

128

146

157

169

174

177

180

185

191

0.00

3.75

15.0

18.2

21.6

25.4

29.4

33.8

38.5

43.4

48.7

54.5

61.2

69.8

82.0

102

137

199

298

422

534

611

657

708

729

743

753

773

800

Radial enthalpy distribution and fuel enthalpy are presented at elevation 32.9 nun

MNximum value of fuel enthalpy is 121.4 cal/g fuel (t-5.96 s)

') All nunerical values are presented at elevation with peak po•wr

H-44
#H16T I Individual R~iacterscs of Refabricated Fuel Rods'.-,

I. (Fresh Fuelj.iiradiated Cadding) under IGR Tests

Table H-3.5. Energy Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel

Rod #H16T

Energy Linear Energy of 1 Clad-to-coolant heat

Time d l) Fuel enthalpy metal-wat)r Leakage of energy) transfer coefficient) T depsitin) pwer (cal/g fuel) reactioni (cakag fuel) as o/M2it

(cag fuel) (kW/m) I (al/ fel

_RAP-T6 I SCANAIR FRAP-T6 FRAP-T6 SCANAIR FRAP-T6 I SCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

0.99

3.97

4.81

5.72

6.72

7.79

8.95

102

11.5

12.9

14A

162

18.5

21.7

26.9

36.2

52.7

78.9

112

141

162

174

188

193

197

199

205

212

0.00

3.42

6.86

7.54

8.22

8.92

9.62

10.3

11.0

11.7

12.5

14.0

17.0

22.7

34.3

58.2

105

183

264

285

219

135

78.3

26.1

15.2

10.3

6.96

2.61

0.19

0.00

0.92

3.45

4.14

4.89

5.70

6.57

7.49

8.48

9.52

10.6

11.8

13.1

14.8

17.3

21.6

29.4

43.4

65.4

90.8

110

120

121

112

99.8

87.2

77.1

46.4

5.62

0.00

0.90

3.52

4.15

4.94

5.81

6.59

7.58

8.61

9.56

10.7

11.9

13.2

15.0

17.3

21.7

28.6

42.9

63.9

89.9

109

115

115

103

91.3

80.0

70.4

42.7

5.71

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.01

0.01

0.01

0.02

0.02

0.03

0.03

0.09

0.31

0.63

1.04

1.54

2.16

2.99

4.20

6.23

9.96

16.7

26.9

38.6

49.7

74.2

92.5

109

121

155

201

0.00

0.00

0.02

0.03

0.04

0.06

0.07

0.09

0.12

0.18

0.46

0.86

1.30

1.89

2.51

3.48

4.67

6.95

10.8

18.3

30.1

42.2

55.8

81.7

99.4

114

127

160

205

0.00

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.49

0.94

1.20

1.46

1.76

2.21

'2.96

4.40

7.27

12.5

19.7

25.5

25.1

23.5

193

16.6

13.5

11.5

6.86

0.14

0.00

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.66

1.16

1.45

1.73

2.13

2.62

3.60

5.17

8.77

14.8

24.1

31.8

33.1

30.4

22.3

17.9

15.0

13.0

7.75

0.13

) All numerical values are presented at elevation %ith peak power

H-45
#H16T J indvdu M • tn•• Re fabic'a'ted FNel'Rods. " , ; (Freh Fuel, Preiqr Cladding) under IGR Rods Tetsd •

Table H-3.6. Temperature Variation, Fission Gas Release and ZrO2 Thickness Vs. Time for Fuel

Rod #H16T Calculated by FRAP-T6 and SCANAIR Codes

Fuel centerline Fuel surface Clad outer Average (s) temperature1) temperature 1) temperature1) thickness

(K) (K) (K)

FRAP-T6_I SCANAIR FRAP-T6 I SCANAIR FRAP-T6 I SCANAIR FRAP-T6

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

310

355

367

380

393

408

423

439

456

4,73

492

514

542

583

650

770

983

1315

1712

2044

2244

2345

2395

2312

2139

1935

1195

389

293

308

352

363

376

389

402

418

434

449

468

487

509

538

575

645

750

965

1279

1690

2035

2217

2322

2335

2200

1991

1770

1108

384

293

308

348

358

369

381

394

407

421

436

450

464

480

500

529

577

659

791

952

1055

1039

1012

973

874

809

786

777

713

386

293

306

345

354

366

378

389

403

418

431

445

460

474

495

521

570

640

770

916

1008

293

297

318

325

332

341

350

361

372

381

385

386

388

389

391

394

399

406

416

426

433

432

431

426

422

417

414

405

377

293

297

317

323

331

340

348

359

370

378

380

381

381

*382

384

386

388

393

401

410

417

418

415

408

404

401

399

392

375

975

912

865

833

822

808

791

697

382 1. 1 1 A. A. I A

" All numerical values are presented at elevation %ith peak power

2) Initial ZrO2 thickness is 5 IPn

H-46
#H16T didua l .Chcte ics of Refabricated Fuel Rods I

:(Fresh F _• erradiated ,d Claddifg) under IGR Tests

Table 11-3.7. Mechanical Characteristics of Fuel Rod #H16T Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes

TimeI Clad outer Fuel hoop Fuel - clad gap II Clad hoop Clad hoop Internal gas (s)i temperature1) strain') width') strain1) stress") pressure

S (K) (%) (mm) (MPa) (MPa)

FRA-T6 IsCAN FRAP-T6 SCAN FRAP-T6 SCANAlR FRAP-T6ISCAN FRAP-T6 SC FRAP.T61SCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

42

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

297

318

325

332

341

350

361

372

381

385

386

388

389

391

394

399

406

416

426

433

432

431

426

422

417

414

405

377

293

297

317

323

331

340

348

359

370

378

380

381

381

382

384

386

388

393

401

410

417

418

415

408

404

401

399

392

375

0.00

0.01

0.05

0.06

0.08

0.09

0.10

0.12

0.13

0.15

0.17

0.19

0.21

0.23

0.27

0.34

0.45

0.67

1.03

1.50

1.88

2.08

2.14

2.07

1.89

1.67

1.46

0.79

0.09

0.00

0.01

0.05

0.06

0.07

0.09

0.10

0.11

0.13

0.14

0.16

0.18

0.20

0.22

0.26

0.33

0.44

0.68

1.06

1.59

1.98

2.12

2.10

1.82

1.56

1.33

1.14

0.64

0.06

0.08

0.08

0.08

0.08

0.08

0.08

0.08

0.08

0.08

0.08

0.08

0.08

0.08

0.07

0.07

0.07

0.07

0.06

0.05

0.03

0.02

0.01

0.00

0.01

0.01

0.02

0.03

0.05

0.08

0.08

0.08

0.08

0.08

0.08

0.08

0.08

0.08

0.08

0.08

0.08

0.08

0.08

0.07

0.07

0.07

0.07

0.06

0.04

0.03

0.01

0.01

0.01

0.02

0.03

0.03

0.04

0.06

0.08

0.01

0.01

0.03

0.03

0.03

0.04

0.05

0.05

0.06

0.07

0.07

0.07

0.07

0.08

0.08

0.08

0.09

0.10

0.11

0.13

0.15

0.15

0.15

0.13

0.13

0.12

0.11

0.10

0.07

0.01

0.01

0.03

0.03

0.04

0.04

0.05

0.06

0.06

0.07

0.07

0.07

0.07

0.08

0.08

0.08

0.09

0.10,

0.12

0.14

0.17

0.17

0.16

0.14

0.13

0.12

0.11

0.09

0.07

8.73 8.70

8.80

8.96

9.00

9.04

9.08

9.12

9.16

9.21

9.25

9.29

9.33

9.37

9.42

9.48

9.58

9.72

9.91

10.1

10.3

10.5

10.6

10.6

10.6

10.6

10.5

10.4

10.0

9.12

8.77

8.97

9.02

9.07

9.12

9.16

9.22

9.27

9.34

9.41

9.47

9.54

9.63

9.75

9.95

10.2

10.8

11.6

12.7

13.5

13.7

13.5

12.7

12.2

11.9

11.6

10.7

9.10

1.70

1.71

1.74

1.75

1.76

1.76

1.77

1.78

1.79

1.79

1.80

1.81

1.82

1.83

1.84

1.85

1.88

1.92

1.96

1.99

2.02

2.03

2.04

2.04

2.03

2.02

2.00

1.94

1.77

1.70

1.71"

1.75

1.75

1.76

1.77

1.78

1.79

1.80

1.81

1.81

1.82

1.83

1.84

1.86

1.88

1.91

1.97

2.03

2.09

2.14

2.16

2.16

2.13

2.11

2.08

2.05

1.97

1.77

' All numerical values are presented at elevation with peak pomer

H-47
#IH16T Individtual Ch'a-r0aci~ifkofRefabricated Fuel Rods'

' (Fresh Fuel, Preirf13"tedCladding) under IGR Tests

Table H-3.8. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #HI6T

Axial interval Energy deposition at infinite time Fuel enthalpy

from-to at time (t-5.96 s)

(mm)-(mm) cal/g fuel J/g fuel per-unit cal/g fuel J/g fuel per-unit

25.8-39.9 216 906 1.00 121 509 1.00

39.9 - 54.0 204 854 0.94 114 479 0.94

54.0-68.1 196 819 0.90 110 460 0.90

68.1-82.2 189 793 0.88 106 445 0.88

82.2-96.3 188 787 0.87 105 442 0.87

96.3-110.4 188 787 0.87 105 442 0.87

110.4 - 124.5 189 792 0.87 106 445 0.87

124.5 - 138.6 192 803 0.89 108 451 .0.89

138.6- 152.7 193 810 0.89 109 455 0.89

152.7 - 166.8 196 820 0.90 110 460 0.90

250

U

200

150 U

= 100 0

~5o

'' '. ' ..... j .. ... . .o . .. .. . . o .- m. oo ... ... ..

- Energy deposition

Fuel enthalpy

0

20 40 60 80 100 12

Axial coordinate (mm)

0 140 160 180

Fig. H-3.4. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6 Code

for Fuel Rod #H16T

H-48
#H16T [ lndividu•al•l cteristics of Refabricated Fuel Rods

-(Frh Fu•.Pirradiated Cladding) undei-IGR Tests 7-.:,:-

1.2

,E

0

1.0

0.8

0.6

0.4

0.2

1 2 3 4

Radial fuel coordinate (mm)

Co

U

C.

C

1.0 1.5 2.0 2.5 3.0 3.5 4.0

Radial fuel coordinate (mm)

Fig. H-3.5. Radial Distributions of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #H16T

H-49
#H16T Individua Chafida=Mi~sbf Refabricate FueIlRods I(Fresh Fuel, Plreirgj'i C addin uner O et

300

240

iE 180

OL12060

0

2500

2000

1500 200

E 1000

I-%

250

200

I

150

100 *

50

0 1 2 3 4 5 6 7 8 9 10

Time (s)

35

28

0

4)

21.1

U 14

0

U

"S

500

0

0 1 2 3 4 5 6 .7 8 9 10

Time (s)

Fig. H-3.6. Energy and Temperature Characteristics Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes for Fuel Rod #1116T

H-50
#H16T Ilndiwdual terstcs of Refabricated Fuel Rods'..

I (FreshFu •jiradiated Cladding) under IGR Tests

2.5

2.0

1.5

1.0

E4.J

0.5

0.0

... "- ..... ..... ... " .....

FRAN-T6

.... SCANAIR

--U- Internal gas pressure

-43- Clad hoop stress

25

20

15~,C.,,

U

.-

10

10

5

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

0.18

0.16

0.14

0.12

0.10

o 0.08

U) 0.06

0.04

0.02

0.00

0.09

(0-

E0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. H-3.7. Cladding Mechanical Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #H16T

H-5I
#H16T Individual Chaartac* is-ofRefabricated Fuel Rods

-(Fresh Fuel, PreiM Cladding) under IGR Tests " ' ,

2.5

2.0

1.5

0

0

o6 1.0

0.5

0.0

2500

2000

1500

0

U

500

0

0 1 2 3 4 5 6 7 )8 9 10

Time (s)

Fig. H-3.8. Fuel Strain Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel Rod N1I16T

H-52
#~H16T I Individt&dramiceristics of Refabricated Fuel Rods 1',r

(Fresh Fu•ý diated Cladding) under IGRTests:.;: "-

Table H1-3.9. Some Results of PIE for Fuel Rod #H16T

Characteristic Value

1. Measured parameters of cladding oxidation and cladding

deformation

1.1. Cladding thickness at elevation 95 mm for different azimuthal

angles (pm):

00 691

900 705

1800 691

2700. 677

1.2. Zr02 thickness at elevation 95 mm for different azimuthal angles

00 5

900 5

1800 5

2700 5

1.3. cZr(O) thickness at elevation 95 mm for different azimuthal angles (pm):

00 0

900 0

1800 0

2700 0

1.4. Clad hoop strain at elevation 95 mm (%) 0

2. Measured parameters for FGR analysis

2.1. Internal gas composition (% by volume):

He

N2

02

Ar

C02

Kr

Xe

2.2. Free gas volume (cm3 ) 6.33

2.3. Gas pressure inside fuel rod under normal condition (MPa) 1.538

2.4. Kr concentration in fuel (cm 3/g fuel)

3. Measured parameters of cladding hydriding

3.1. Coefficient of hydride orientation (per-unit)

3.2. Hydrogen concentration (% by weight)

H-53
#H16T IndividuA Chmcrtlt§ of Refabricatc'd Fuel Rods

(Freish Fuel,-Preirr•.( Cladding) under IGR Tests..-'

Table H-3.10. General Characteristic of Fuel Rod #1116T

Parameter Unit Value

Experiment FRAP-T6 SCANAIR

I Type of coolant - water water water

2 Bumup MWd/kg U 0 0 0

3 Energy deposition in fuel rod cal/g fuel 195 195 195

4 Peak fuel enthalpy - cal/g fuel - 121 115

5 Peak fuel temperature K - 2400 2358

6 Peak clad temperature K - 433 418

7 Fuel rod failure Yes, No No No

8 Type of failure:

- cladding rupture due to ballooning Yes, No No No

- cladding rupture due to PCMI Yes, No No No

- fragmentation of fuel rod Yes, No No -

9 Failure time s - -

10 Fuel enthalpy at failure cal/g fuel - -

11 Outer cladding temperature at failure K - -

12 Internal gas pressure at failure MPa - -

13 ZrO2 thickness after test Pm .5 5 -

14 Residual clad hoop strain:

- peak value for ballooning area % - -

- other locationt) % 0 0 0

')Calculated values by FRAP-T6 and SCANAIR codes are average along height of fuel rod excluding ballooning region

H-54
rýilkdir idlum

APPENDL

Ic RM 7TnnderGuea

H-55
#H17T !Inrdhividual, Par s n ue td Fuel-Rods GefaMiad T I(Fresh Fuel, Prirrad 2Qq.C-jaddini) under IGR Tests".'

I)

U

U

U

0

T

Axial coordinate (mm)

Fig. 11-4.1. Appearance of Fuel Rod #1117T (photographs and X-ray photograph) and Profilometry

H-56
#H17T ( ad ie ati' of R ndabricad Fuel Rods

F Cladding) u~ndir IOR TestiU

11

Fig. 11-4.2. Cross-Section and Cladding Microstructure for Fuel Rod #1117T at 90 mm Elevation

H-57

I .....
#H17T ;i Idivid'u ýCha ýýýf'Refabri'catced Fuel Rd 2;.I

ýFfrcshkti-ueit=V-' l~ding) unde-r IGR-T ess ý--

Position 1 Mn

Position2

Fig. 11-4.3. Fuel Microstructure for Fuel Rod #H17T at 90 mm Elevation

H-58
#H17T I lndivid~~i~iC stics of Refabricaed Fuel Rods

S(Fa Cladding) under IGRTestsc ,

Table 11-4.1. Time Dependent Energy Characteristics of Fuel Rod #H17T

Reactor Cumulative number of fissions Power of Energy deposition

Time energy in fuel rod (fiss) fuel rod in fuel rod

(s) deposi- 235 0 Total (kW) cal/g fuel J/g fuel

tin x10"14 x 10,1

2 x10"14 NI

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

9.0

10.0

20.0

30.0

0o

0.000

0.231

1.510

1.920

2.370

2.880

3.450

4.100

4.860

5.800

7.060

8.900

11.80

16.90

25.50

38.70

54.40

68.30

78.20

84.30

87.90

90.10

91.50

93.60

94.80

95.50

96.00

96.70

97.20

98.70

99.20

100.0

0.000

0.028

0.181

0.230

0.284

0.345

0.414

0.491

0.582

0.695

0.846

1.070

1.420

2.020

3.060

4.640

6.520

8.190

9.380

10.10

10.50

10.80

11.00

11.20

11.40

11.40

11.50

11.60

11.60

11.80

11.90

12.00

0.000

0.010

0.064

0.082

0.101

0.123

0.147

0.175

0.207

0.247

0.301

0.380

0.505

0.720

1.090

1.650

2.320

2.910

3.340

3.600

3.750

3.840

3.900

3.990

4.040

4.070

4.090

4.120

4.150

4.210

4.230

4.270

0.000

0.028

0.181

0.230

0.285

0.347

0.415

0.493

0.584

0.697

0.849

1.070

1.420

2.603

3.070

4.660

6.540

8.220

9.410

10.10

10.60

10.80

11.00

11.30

11.40

11.50

11.50

11.60

11.70

11.90

11.90

12.00

0.000

0.216

0.650

0.733

0.817

0.910

1.020

1.180

1.410

1.810

2.520

3.840

6.370

11.10

18.50

25.60

26.10

20.50

13.30

7.890

4.700

2.990

2.060

1.090

0.681

0.461

0.332

0.251

0.170

0.035

0.017

0.000

0.000

0.316

2.070

2.630

3.260

3.950

4.740

5.620

6.670

7.960

9.690

12.20

16.20

23.20

35.00

53.10

74.50

93.70

107.0

116.0

121.0

124.0

126.0

129.0

131.0

132.0

133.0

134.0

135.0

138.0

139.0

141.0

0.000

1.320

8.670

11.00

13.60

16.50

19.80

23.50

27.90

33.30

40.60

51.10

67.80

97.10

147.0

222.0

312.0

392.0

448.0

486.0

507.0

519.0

527.0

540.0

548.0

553.0

557.0

561.0

565.0

578.0

582.0

590.0 I J. .1.

Maximum value of power is 26.8 kW (t - 4.70 s)

1) Current energy deposition per maximum energy deposition (at infinite time)

H-59
#H17T I Individuel . R ore ed ariad d uelGRoss 'I

(frc~lh Fut,'id iC;adig under IGR Ts

Table 11-4.2. Axial Energy Characteristics of Fuel Rod #H17T

Axial Cumulative number of fissions Maximum Energy deposition

coordinate at axial interval (fiss) power of at infinite time*

from lower U23

5 U23 Total fuel rod callg fuel J/g fuel per-unit3 )

end of fuel x10 X10- 1

, XI0-1 3 (k'W)

rod I × t=4.70s

(mm)

15.0

20.0')

25.0

30.0

35.0

40.0

45.0

50.0

55.0

60.0

65.0

70.0

75.0

80.0

85.0

90.0

95.0

100.0

105.0

110.0

115.0

120.0

125.0

130.0

135.0

140.0

145.0

150.0

155.0

160.02)

165.0

0.000

3.090

4.880

4.760

4.620

4.520

4.430

4.350

4.320

4.260

4.210

4.100

4.060

4.070

4.060

4.070

4.090

4.090

4.090

4.100

4.090

4.100

4.120

4.170

4.180

4.200

4.220

4.150

4.060

2.410

0.000

0.000

0.900

1.460

1.470

1.470

1.480

1.490

1.500

1.520

1.530

1.540

1.520

1.530

1.540

1.550

1.560

1.580

1.580

1.580

1.570

1.560

1.550

1.540

1.540

1.520

1.500

1.480

1.430

1.370

0.795

0.000

0.000

3.100

4.890

4.770

4.630

4.530

4.450

4.370

4.330

4.270

4.220

4.110

4.080

4.090

4.070

4.090

4.110

4.110

4.110

4.110

4.110

4.110

4.130

4.190

4.200

4.210

4.240

4.160

4.080

2.410

0.000

0.000

0.692

1.090

1.070

1.030

1.010

0.993

0.975

0.966

0.953

0.943

0.918

0.910

0.912

0.909

0.912

0.916

0.916

0.916

0.918

0.916

0.918

0.922

0.934

0.937

0.940

0.946

0.929

0.910

0.539

0.000

0.000

165.0

161.0

157.0

154.0

151.0

147.0

144.0

142.0

140.0

139.0

138.0

136.0

136.0

136.0

136.0

135.0

135.0

135.0

136.0

136.0

136.0

137.0

137.0

138.0

S139.0

140.0

140.0

140.0

140.0

0.000

0.000

691.0

674.0

657.0

645.0

632.0

615.0

603.0

594.0

586.0

582.0

578.0

569.0

569.0

569.0

569.0

565.0

565.0

565.0

569.0

569.0

569.0

573.0

573.0

578.0

582.0

586.0

586.0

586.0

586.0

0.000

0.00

1.00

0.98

0.95

0.93

0.92

0.89

0.87

0.86

0.85

0.84

0.84

0.82

0.82

0.82

0.82

0.82

0.82

0.82

0.82

0.82

0.82

0.83

0.83

0.84

0.84

0.85

0.85

0.85

0.85

0.00 I

All numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate .l: 2.5 mm

1) Initial coordinate of fuel is 19.4 mm

2) End coordinate of fuel is 160.4 mm

3) Current value per ma'ximum value

H-60

I --
#H17T I ndiv'idiiaf rstics of Refabrcated 'Fuel* o1ds') l >2

(Fres Fýý faed Cladding) Gaheir IGRTessW

Table H1-43. Radial Energy Characteristics of Fuel Rod #H17T

Coordinates of fuel zones (mm)

Characteristics* I zone 2 zone 3 zone 4 zone

1.10-2.12 2.12-2.79 2.79-3.32 3.32 -3.79

Number of fissions x 10"14 (fiss) 2.880 2.920 3.030 3.160

Power of fuel rod') (kW) 6.430 6.510 6.760 7.050

U235 Energy deposition2) (callg fuel) 135.0 137.0 142.0 149.0

Energy deposition2

) (J/g fuel) 565.0 573.0 594.0 624.0

Energy deposition3) (per-unit) 0.906 0.919 0.953 1.000

Number of fissions x 10"12 (fiss) 1.070 1.080 1.070 1.040

Power of fuel rodt) (kW) 0.023 0.024 0.024 0.023

U 2 38 Energy deposition2

) (cal/g fuel) 0.495 0.503 0.498 0.484

Energy deposition2) (J/g fuel) 2.070 2.110 2.080 2.030

Energy deposition3) (per-unit) 0.984 1.000 0.990 0.962

Number of fissions x 104 4 (fiss) 2.890 2.930 3.040 3.170

Power of fuel rod') (kW) 6.450 6.530 6.780 7.080

Total Energy deposition2) (cal/g fuel) 136.0 138.0 143.0 149.0

Energy deposition2) (J/g fuel) 569.0 578.0 599.0 624.0

Energy deposition3) (per-unit) 0.913 0.926 0.960 1.000

I) at time of 4.70 s, 2) at infinite time, 3) Current value per maximum value

All numerical values of characteristics were calculated for length of fuel stack

H-61

I ....
#H17T lJn~divi~du"l ChuAra~~fe:***'Re fabric-ated FU-el ko~di"

(Freh FelPre~i~~d~addng)un~ler IGR Tists

Table 11-4.4. Fuel Enthalpy Vs. Time Calculated by FRAP-T6 Code for Fuel Rod #II17T

Time Enthalpy at fuel radius Fuel e Energy deposition

Tim _(Eal/&_ fuel)_Fuel ent _lp ) in fuel rod

(s) 1.10.a.. 2.22mm I 2.89mm 3.79mm cal/gfuel Jigfuel cal/g fuelJ igfuel

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4A

4.6

4.8

5.0

5.2

5A

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

0.35

2.13

2.69

3.30

3.98

4.73

5.58

6.59

7.84

9.56

12.1

163.

23.5

35.9

55.1

77.8

97.9

112

120

123

123

121

110

942

78.9

65.5

33.1

5.29

0.00

0.35

2.11

2.65

3.25

3.92

4.66

5.49

6.48

7.73

9.43

12.0

16.1

23.2

35.5

54.3

76.4

95.3

107

112

111

108

103

88.7

75A

63.9

54.3

29.7

528

0.00

0.34

2.05

2.57

3.16

3.80

4.52

5.33

6.29

7.50

9.16

11.6

15.6

22.4

34.1

51.8

71.3

85.8

91.6

90.4

85.7

79.8

73.9

61.8

53.3

46.7

41.1

25.2

5.25

0.00

0.31

1.88

2.37

2.91

3.50

4.16

4.92

5.80

6.90

8.39

10.5

13.7

18.8

26.7

36.4

43.0

43.6

41.3

39.0

36.4

34.0

31.9

29.1

27.8

26.5

25.1

18.6

5.19

0.00

0.34

2.05

2.58

3.16

3.81

4.53

5.34

6.30

7.51

9.16

11.6

15.5

22.2

33.6

50.4

68.9

82.6

89.4

90.7

88.7

85.2

81.1

70.5

61.1

52.8

45.6

26.5

525

'0.00

1A3

8.58

10.8

13.2

16.0

19.0

22.4

26.4

31.5

38.4

48.6

64.9

92.9

141

211

289

346

374

380

372

357

340

295

256

221

191

111

22.0

0.00

0.32

2.07

2.63

3.25

3.95

4.73

5.62

6.66

7.95

9.68

12.2

16.2

23.1

35.0

53.0

74.5

93.6

107

116

121

124

126

129

130

132

132

134

138

0.00

1.32

8.65

11.0

13.6

16.6

19.8

23.5

27.9

33.3

40.6

51.1

68.0

97.0

147

222

312

392

449

485

506

518

527

539

547

551

555

563

580 ____ .1 _____ .L I I _____ I 1. _____ .L _____ L

Radial enthalpy distribution and fuel enthalpy are presented at elevation 26.4 mm

Maxinunm value of fuel enthalpy is 90.7 calg fuel (t=5.36 s)

1) All numerical values are presented at elevation %iith peak povr

H-62
#H17T I (Fresh F ated Cladding) under IGR Tests .''-:

Table 11-4.5. Energy Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel

Rod #H17T

Energy Linear Energy of Clad-to-coolant heat

T deposition') por') Fuel enthalpy') metal-water Leakage of energy transfer coefficienti) depsitin_)_P___r__ (cal/g fuel) reaction__ (ea fuel)______ ___g 

(s) (cal/g fuel) (kW/m) (ca/g fuel) reactioni) (cal/g fuel) (kW/m2

K)

FRAP-T6 ISCANAIR I AP-T6 FRAP-T6 SCANAIR FRAP-T6 SCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5A

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

0.36

2.34

2.97

3.68

4.47

5.35

6.36

7.53

8.99

11.0

13.8

18.4

26.2

39.6

60.0

84.2

106

121

131

136

140

142

146

148

149

150

152

157

0.00

1.72

5.17

5.83

6A9

7.23

8.11

9.38

11.2

14.4

20.0

30.5

50.6

88.2

147

203

'207

163

106

62.7

37.4

23.8

16.4

8.66

5.41

3.66

2.64

1.35

0.14

0.00

0.34

2.05

2.58

3.16

3.81

4.53

5.34

6.30

7.51

9.16

11.6

15.5

22.2

33.6

50.4

68.9

82.6

89.4

90.7

88.7

85.2

81.1

70.5

61.1

52.8

45.6

26.5

5.25

0.00

0.32

2.10

2.58

321

3.90

4.56

5.43

6.46

7.57

9.32

12.0

15.9

23.1

33.6

51.3

67.9

82.3

88.5

89.1

86.3

82.9

78.6

68.5

60.1

52.1

45.2

26.7

5.44

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.01

0.01

0.01

0.02

0.02

0.03

0.04

0.24

0.74

1.66

3.34

6.49

12.0

19.8

29.0

37.8

46.0

53.4

60.1

74.3

85.3

94.4

102

123

148

-0.00

0.00

0.01

0.02

0.02

0.03

0.04

0.06

0.07

0.09

0.12

0.35

0.90

1.95

3.55

6.95

11.9

20.2

29.4

39.2

48.1

54.8

61.7

75.6

86.2

95.6

103

125

151

0.00

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.16

1.17

2.12

3.61

6.30

10.8

162

202

21.0

19.7

18.2

16.7

15.5

12.4

103

8.75

7.55

4.32

0.09

0.00

0.10

0.10

0.10

0.10'

0.10

0.10

0.10

0.10

0.10

0.10

1.46

2.50

4.36

7.20

12.7

18.5

23.6

25.0

23.6

21.2

19.2

17.2

13.9

11.8

10.1

8.72

4.99

0.10 I _______ I _____ I _____ I _____ £ J. _____ 1. .1

1) All nunerical values are Presented at elevation ¶vith peak power

H-63

I --
#H17T rindiv~didul 'Cha-ýirrloat irtýfabri.Cated Fuel R-ods

.(Fresh Fuel Prei a ý74tfdding) uinder IGRi Tests

Table H14.6. Temperature Variation, Fission Gas Release and ZrO2 Thickness Vs. Time for Fuel

Rod #MO17T Calculated by FRAP-T6 and SCANAIR Codes

Average

Time Fuel centerline Fuel surface Clad outer ZrO2ag) (s) temperature1) temperature1 ) temperature thickness

(K) (K) (K)

FRAP-T6 SCANAIR FRAP-T6 SCANAIR FRAP-T6 SCANAIR FRAP-T6

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

293

299

330

340

350

361

373

387

403

422

449

487

548

652

825

1082

1377

1629

1798

1889

1927

1929

1905

1771

1583

1390

293

299

329

337

348

359

370

384

401

419

447

489

551

665

826

1100

1369

1640

1808

1901

1931

1925

1891

1741

1565

1379

293

299

326

334

343

353

364

376

390

408

431

463

510

585

697

831

920

929

897

866

831

798

769

730

712

694

674

582

380

293

298

324

331

340

350

359

371

386

401

424

457

502

578

673

800

869

876

844

809

784

770

757

735

715

692

669

575

378

293

295

308

313

319

326

334

342

352

364

378

386

391

396

404

413

421

427

428

426

424

422

420

416

412

409

407

398

376

293

294

307

311

317

324

330

339

349

359

373

381

383

387

391

398

404

409

411

409

407

405

403

400

397

395

393

388

374

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

8.0

10.0

30.0

1218

785

382

1214

791

380 I J. .4

I) All numerical values arc presented at elevation with peak power

2) Initial ZrOz2 thickness is 5 pxm

H-64
#H17T Indivdvidl • zscs of Refabricated Fuel Rods:i :.-

] (FreshF 4 i•ClatedClding)under IGR Tests' -

Table 11-4.7. Mechanical Characteristics of Fuel Rod #H17T Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes

Clad outer Fuel hoop Fuel - clad gap Clad hoop Clad hoop Internal gas Time temperatureU strain t i 1 width') straini) stress' pressure

(s) (K) (%) (mm) N%) (MPa) (MPa)

-FRAPT6 SCANAII FRAP-T6 ISCANAIR W -T6 SCANAIR FRAP-T61SCANAIR FRAP-T6TSCANAIR FRAP-T6 SCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

293

295

308

313

319

326

334

342

352

364

378

386

391

396

404

413

421

427

.428

426

424

422

420

416

412

409

407

398

376

293

294

.307

311

317

324

330

339

349

359

373

381

383

387

391

398

404

409

411

409

407

405

403

400

397

0.00

0.00

0.03

0.04

0.05

0.06

0.07

0.08

0.10

0.12

0.15

0.18

0.24

0.34

0.51

0.78

1.10

1.37

1.53

1.59

1.59

1.55

1.49

1.31

1.12

0.94

0.79

0.43

0.08

0.00

0.00

0.03

0.04

0.05

0.06

0.07

0.08

0.09

0.11

0.14

0.18

0.24

0.35

0.52

0.83

1.13

1.41

1.53

1.54

1.48

1.40

1.31

1.10

0.94

0.80

0.68

0.38

0.06

0.07

0.07

0.06

0.06

0.06

0.06

0.06

0.06

0.06

0.06

.0.06

0.06

0.06

0.06

0.05

0.04

0.03

0.02

0.01

0.01

0.01

0.01

0.01

0.02

0.03

0.03

0.04

0.05

0.06

0.07

0.07

0.06

0.06

0.06

0.06

0.06

0.06

0.06

0.06

0.06

0.06

0.06

0.05

0.05

0.04

0.03

0.02

0.01

0.01

0.01

0.02

0.02

0.03

0.03

0.04

0.04

0.05

0.07

0.01

0.01

0.02

0.02

0.03

0.03

0.04

0.04

0.05

0.06

0.07

0.07

0.08

0.08

0.09

0.11

0.12

0.14

0.14

0.13

0.13

0.13

0.12

0.11

0.11

0.10

0.10

0.09

0.06

0.01

0.01

0.02

0.02

0.03

0.03

0.03

0.04

0.05

0.06

0.07

0.07

0.08

0.08

0.09

0.11

0.13

0.14

0.15

0.14

0.13

0.13

0.12

0.11

0.11

0.10

0.10

0.09

0.07

8.71

8.73

8.84

8.88

8.91

8.95

8.98

9.02

9.07

9.12

9A8

9.26

9.37

9.51

9.70

9.90

10.1

10.2

10.3

10.3

10.3

10.3

10.3

10.2

10.1

10.0

9.95

9.66

9.06

8.69

8.71

8.85

8.89

8.93

8.98

9.02

9.07

9.13

9.19

9.28

9.45

9.65

.10.00

10.5

11.2

11.9

12.5

12.7

12.6

12.4

.12.2

11.9

11.6

11.3

11.0

10.8

10.1

9.05

1.70

1.71

1.73

1.73

1.74

1.74

1.75

1.76

1.77

1.78

1.79

1.80

1.82

1.85

1.88

1.92

1.95

1.97

1.98

1.99

1.99

1.99

1.99

1.97

1.96

1.94

1.93

1.87

1.77

1.70

1.71

1.73

1.74

1.74

1.75

1.76

1.77

1.78

1.79

1.80

1.82

1.85

1.88

1.93

1.99

2.03

2.07

2.09

2.09

2.08

2.08

2.07

2.04

2.02

2.00

1.97

1.90

1.77

7.0

7.5

8.0

10.0

30.0

395

393

388

374

1All numerical values arc presented at elevation uith peak polvr

H-65
#H17T iidividuM ~al qfrScfRfb~a FuelRs

Table 11-4.8. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #H17T

Axial interval Ee deposition at infinite time Fuel enthalpy

from-to argyt time (t=5.36 s)

(mm)-(mm) calfg fuel Jig fuel per-unit cal/g fuel J/g fuel per-unit

19.4-33.5 160 670 1.00 90.7 380 1.00

33.5 -47.6 150 630 0.94 85.3 357 0.94

47.6- 61.7 142 596 0.89 80.7 338 0.89

61.7-75.8 138 578 0.86 78.3 328 0.86

75.8 - 89.9 136 570 0.85 77.2 323 0.85

89.9- 104.0 135 566 0.85 76.7 322 0.85

104.0 - 118.1 136 569 0.85 77.1 323 0.85

118.1 - 132.2 137 573 0.86 77.6 325 0.86

132.2- 146.3 139 582 0.87 78.8 330 0.87

146.3 - 160.4 140 587 0.88 79.5 333 0.88

180

U

S150

,- 120

S90

;=-6060

30

0. 0

. .,.. . . .. . .I

[I . Energy deoion

.... Fuel enthalpy

0 20 40 60 80 100

Axial coordinate (mm)

120 140 160 180

Fig. H-4.4. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6 Code

for Fuel Rod #H17T

H-66
#H17T .Frsh euIA nfdated Cladding) 16,der IGR Te&,4*

1.2

i

C)

ii

0

1.0

0.8

0.6

0.4

0.2 II

1 2 3 4

Radial fuel coordinate (mm)

4)

C)

C1.0 1.5 2.0 2.5 3.0 3.5 4.0

Radial fuel coordinate (mm)

Fig. H-4.5. Radial Distributions of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #H17T

H-67
#H17T 1ndividud Chaia~nsdIof Refa-bricateýd Fue Rod

"(Fr~sh Fuel, Pr4M~ajiated Cidding) un~der IGR Ts

250

200

-150

1oo

50

0

2000

1600

1200

E 800

400

0

200

160

120 2

80 "

40

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

25

20

0

15 ;

4;

10

0

U

f4

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. H-4.6. Energy and Temperature Characteristics Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes for Fuel Rod #H17T

H-68
#H17T • ndivF•dha•!•-5.-_iisaticsiefdlad d uel tu;l ods ).2a '.d[

(iFiih F~c;Ou dated Cladding) unrde~r'IGR Tests

2.4

2.0

1.6

S1.2

E 0.8

0.4

0.0

20

16

12-

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

C.

0

0

*0

P.

E

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. H-4.7. Cladding Mechanical Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #H17T

H-69
#H17T

2.0

1.6

• 1.2

0

o 0.8

0.4

0.0

Individ.al Ch~dRefabricated Fuel Ro•s

I,(FeshFel, [adg UndIG u Tests -

- - 2000

- , _____ 1600

1200

E

800 :

40

-400 •- 

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. 11-4.8. Fuel Strain Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel Rod #H17T

H-70
#H17T I[ .fR&MSOUM"teti'itics o ed Fuel RodsR-iabr

(Fi.:t",resýFureT7ated C-laddi'ng) u-nde'rIGR Testsi-'

Table 11-4.9. Some Results of PIE for Fuel Rod #1H17T

Characteristic Value r t

1.1.

1.2.

1.3.

1.4.

Measured parameters of cladding oxidation and cladding

deformation

Cladding thickness at elevation 90 mm for different azimuthal

angles (pm):

00

900

1800

2700

ZrO2 thickness at elevation 90 mm for different azimuthal angles

(Pm):

00

900

1800

2700

cxZr(O) thickness at elevation 90 mm for different azimuthal angles

(Pm):

00

900

1800

2700

Clad hoop strain at elevation 90 mm (%)

705

691

691

710

5

5

5

5

0

0

0

0

1.5

2.

2.1.

2.2.

2.3.

2.4.

Measured parameters for FGR analysis

Internal gas composition (% by volume):

He

N2

02

Ar

CO2

Kr.

Xe

Free gas volume (cm3)

Gas pressure inside fuel rod under normal condition (MPa)

Kr concentration in fuel (cm 3/a fuel)

6.1

1.735

3. Measured parameters of cladding hydriding

3.1. Coefficient of hydride orientation (per-unit) 0.29

3.2. Hydrogen concentration (% by weight)

H-71
#H17T I.'ndvdual C i fRefabicated Fuel Rodsn,-.-IGR T : (Fresh• Fuel,-Pre•ijaedldding) under: IGR Tts:•i•!!=• :

Table H-4.10. General Characteristic of Fuel Rod #1117T

Parameter Unit Value

Experiment FRAP-T6 SCANAIR

I Type of coolant - water water water

2 Burnup MWd/kg U 0 0 0

3 Energy deposition in fuel rod cal/g fuel 141 141 141

4 Peak fuel enthalpy cal/g fuel - 91 89

5 Peak fuel temperature K - 1931 1932

6 Peak clad temperature K - 428 411

7 Fuel rod failure Yes, No No No

8 Type of failure:

- cladding rupture due to ballooning Yes, No No No

- cladding rupture due to PCMI Yes, No No No

- fragmentation of fuel rod Yes, No No -

9 Failure time s - -

10 Fuel enthalpy at failure cal/g fuel - -

11 Outer cladding temperature at failure K - -

12 Internal gas pressure at failure MPa - -

13 ZrO2 thickness after test j-M 5 5

14 Residual clad hoop strain:

- peak value for ballooning area % - .

- other locationt) V. 1.5 0 0

')Calculated values by FRAP-T6 and SCANAIR codes are average along height of fuel rod excluding ballooning region

H-72
>4S S

APPEAW

..ristic& fort lii ~

H-73
#H18T, Iniresiu FueR• efýa6bianed FuIel Ro-dse

i Fsh Fuel, Pr deriGRTeii tin'f Y"...ild

Fig. H-5.1. Appearance of Fuel Rod #1118T (photographs and X-ray photograph)

H-74
#H18T I izdiviuai~~~isicsof Refabr~icaýicd Ful ý od6

:(FrehPic~dae Ch~ding) un~der IOR Tcits>~

Position I

Fig. H-5.2. Cross-Section and Cladding Microstructure for Fuel Rod #1118T at 90 mm Elevation

H-75

I ....
#H18T .In lividual Chaz r,__=Sbofgefabr-icat ed'Ftie Rkios

:(Fresh Fuel.ým7U Prirdac~dink).6iderIGR'Teitis'ý

Position 1
#H18T yi~d~iv'd-- =tcnitics of Refabricated Fuel Rods

Table H-5.1. Time Dependent Energy Characteristics of Fuel Rod #H18T

Reactor Cumulative number of fissions Power of Energy deposition

Time energy in fuel rod (fiss) fuel rod in fuel rod

(s) deposi- U7.31 f Total (kW) calg fuel J/g fuel

tion) Xl0,14 X10,12 x10"14

N%

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

9.0

10.0

20.0

30.0

0o

0.000

1.080

4.410

5.600

7.430

10.80

17.40

29.20

45.20

60.80

72.10

79.50

84.30

87.40

89.60

91.20

92.40

93.20

93.90

94.50

94.90

95.30

95.60

96.20

96.60

96.90

97.20

97.60

97.90

99.20

99.60

100.0

0.000

0.121

0.492

0.624

0.829

1.200

1.940

3.260

5.040

6.780

8.040

8.860

9.400

9.750

10.00

10.20

10.30

10.40

10.50

10.50

10.60

10.60

10.70

10.70

10.80

10.80

10.80

10.90

10.90

11.10

11.10

11.20

0.000

0.043

0.175

0.222

0.295

0.428

0.691

1.160

1.790

2.410

2.860

3.150

3.350

3.470

3.560

3.620

3.670

3.700

3.730

3.750

3.770

3.780

3.800

3.820

3.840

3.850

3.860

3.870

3.890

3.940

3.950

3.990

0.000

0.121

0.494

0.627

0.832

1.210

1.950

3.270

5.060

6.800

8.070

8.900

9.430

9.790

10.00

10.20

10.30

10.40

10.50

10.60

10.60

10.70

10.70

10.80

10.80

10.80

10.90

10.90

11.00

11.10

11.10

11.20

0.000

0.681

1.580

2.240

3.740

7.240

14.20

22.70

26.40

21.50

14.40"

9.330

6.140

4.190

2.970

2.180

1.650

1.290

1.040

0.853

0.695

0.588

0.502

0.355

0.266

0.211

0.176

0.149

0.117

0.030

0.015

0.000

0.000

1.380

5.630

7.140

9.480

13.80

22.20

37.20

57.60

77.40

91.90

101.0

108.0

112.0

115.0

117.0

118.0

119.0

120.0

121.0

122.0

122.0

123.0

123.0

124.0

125.0

125.0

126.0

126.0

128.0

129.0

132.0

0.000

5.780

23.60

29.90

39.70

57.80

92.90

156.0

241.0

324.0

385.0

423.0

452.0

469.0

481.0

490.0

494.0

498.0

502.0

507.0

511.0

511.0

515.0

515.0

519.0

523.0

523.0

527.0

527.0

536.0

540.0

553.0

I

Maximum value of power is 26.4 kW (t 3.20 s)

1) Current energy deposition per maximum energy deposition (at infinite time)

H-77
#H18T 4A;1V'diviidI Char-i~ndfRifalbricated Fe os I (Fresh ýFuel, PrOVid M-1 ddinj)' uerIGTes .

Table U-5.2. Axial Energy Characteristics of Fuel Rod #H18T

Axial Cumulative number of fissions Maximum Energy deposition

coordinate at axial interval (fiss) power of at infinite time*

from lower U235 U238 Total fuel rod cal/g fuel J/g fuel per-unit 3

)

end of fuel x10-" X101 Xl1 3 (kJ )

rod i t=3.20 s

(ram)

20.0

25.01)

30.0

35.0

40.0

45.0

50.0

55.0

60.0

65.0

70.0

75.0

80.0

85.0

90.0

95.0

100.0

105.0

110.0

115.0

120.0

125.0

130.0

135.0

140.0

145.0

150.0

155.0

160.0

165.02)

170.0

0.000

2.580

4.510

4.430

4.400

4.300

4.150

4.070

3.990

3.940

3.900

3.900

3.880

3.830

3.800

3.780

3.780

3.780

3.830

3.830

3.830

3.830

3.850

3.850

3.860

3.900

3.920

3.910

3.880

2.500

0.000

0.000

0.751

1.350

1.360

1.400

1.410

1.390

1.400

.1.400

1.410

1.420

1.450

1.450

1.450

1.450

1.450

1.460

1.460

1.470

1.470

1.460

1.450

1.440

1.420

1.410

1.400

1.380

1.350

1.310

0.825

0.000

0.000

2.590

4.530

4.440

4.410

4.320

4.160

4.090

4.000

3.950

3.910

3.910

3.890

3.840

3.810

3.800

3.790

3.790

3.840

3.850

3.840

3.850

3.870

3.860

3.880

3.910

3.940

3.930

3.890

2.510

0.000

0.000

0.609

1.060

1.040

1.040

1.010

0.978

0.961

0.940

0.929

0.920

0.920

0.914

0.903

0.895

0.892

0.891

0.891

0.903

0.904

0.903

0.904

0.908

0.908

0.911

0.920

0.926

0.923

0.914

0.589

0.000

0.000

154.0

151.0

147.0

144.0

141.0

138.0

136.0

133.0

132.0

130.0

128.0

128.0

-127.0

127.0

126.0

126.0

126.0

126.0

127.0

127.0

127.0

128.0

128.0

129.0

130.0

131.0

131.0

131.0

131.0

0.000

0.000

645.0

632.0

615.0

603.0

590.0

578.0

569.0

557.0

553.0

544.0

536.0

536.0

532.0

532.0

527.0

527.0

527.0

527.0

532.0

532.0

532.0

536.0

536.0

540.0

544.0

548.0

548.0

548.0

548.0

0.000

0.00

1.00

0.98

0.95

0.94

0.92

0.90

0.88

0.86

0.86

0.84

0.83

0.83

0.82

0.82

0.82

0.82

0.82

0.82

0.82

0.82

0.82

0.83

0.83

0.84

0.84

0.85

0.85

0.85

0.85

0.00

All numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate + 2.5 mm

!) Initial coordinate of fuel is 24.7 mm

2) End coordinate of fuel is 165.7 mm

3) Current value per maximum value

H-78
#H18T I indiidi~P~~sticsof RkefaVricated FuelRod

[.'AFm~shIJ~ Cladding) under IGR Tests .-'

Table H-5.3. Radial Energy Characteristics of Fuel Rod #HIST

Coordinates of fuel zones (mm)

Characteristics* I zone 2 zone 3 zone 4 zone

1.10 -2.12 2.12-2.79 2.79-3.32 3.32-3.79

Number of fissions x10"14 (fiss) 2.690 2.730 2.830 2.950

Power of fuel rod') (kW) 6.320 6.410 6.650 6.940

U23 Energy deposition 2

) (calg fuel) 126.0 128.0 133.0 139.0

Energy deposition2 ) (J/g fuel) 527.0 536.0 557.0 582.0

Energy deposition3) (per-unit) 0.906 0.921 0.957 1.000

Number of fissions X10"12 (fiss) 0.997 1.010 1.000 0.974

Power of fuel rod') (kW) 0.023 0.023 0.023 0.023

U238 Energy deposition2) (ca~lg fuel) 0.462 0.470 0.465 0.452

Energy deposition2) (J/g fuel) 1.930 1.970 1.950 1.890

Energy deposition3) (per-unit) 0.983 1.000 0.989 0.962

Number of fissions xI0"14 (fiss) 2.700 2.740 2.840 2.960

Power of fuel rod1 ) (kW) 6.350 6.430 6.680 6.960

Total Energy deposition2) (cal/g fuel) 127.0 129.0 133.0. 139.0

Energy deposition2) (J/g fuel) 532.0 540.0 557.0 582.0

Energy deposition3) (per-unit) 0.914 0.928 0.957 1.000

1)at time'of 3.20s, 2) at infinite time. 3) Current value per maximum value

• All numerical values of characteristics were calculated for length of fuel stack

H-79
#H18T Individual tfharact icsbfRefabricated Fuel Rods o I

ý(Fresh Fuelý Preii•.; tCladding) under IGR Tests '

Table 11-5.4. Fuel Enthalpy Vs. Time Calculated by FRAP-T6 Code for Fuel Rod 1IIN8T

Time Enthalpy at fuel radius Fuel n Energy deposition

(ca4/[ fuel) _ FueI nta__ _ ) in fuel rod

(s) 1.10mm 2.22 mm 2.89 mm 3.79 mm cal/gifuel ig fuel cal/gfuel JIgfuel

0.0

1.0

2.0

2.2

2A

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5A

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

1.51

5.83

7.37

9.82

14.4

23.6

40.2

62.8

84.7

100

110

115

116

116

113

110

105

99.2

93.5

87.7

81.9

76.3

63.3

53.2

44.4

37.8

21.2

5.23

0.00

1.48

5.71

7.22

9.63

14.2

23.3

39.6

61.5

82.3

96.0

103

105

103

99.7

95.2

90.3

85.2

80.2

75.4

70.8

66.4

62.3

52.7

45.3

38.6

33.4

19.7

522

0.00

1.43

5.48

6.94

9.25

13.6

22.3

37.7

57.6

74.8

83.4

84.7

82.0

77.6

72.8

68.1

63.9

60.1

56.7

53.6

50.8

48.3

45.9

40.2

35.7

31.3

27.8

17.6

5.19

0.00

1.29

4.96

6.26

8.29

12.0

18.6

28.7

38.3

42.2

40.9

38.0

35.7

33.6

31.9

30.7

29.8

29.1

28.5

27.9

27.4

26.9

26.3

24.8

23.2

21.5

19.8

14.1

5.14

0.00

1.43

5.50

6.96

9.27

13.6.

22.2

37.1

56.2

72.6

81.5

84.5

84.2

82.0

79.0

75.5

71.8

68.2

64.6

61.1

57.8

54.6

51.6

44.4,

38.8

33.5

29.4

18.1

5.20

0.00

6.00

23.1

29.2

38.9

57.0

92.8

155

235

304

341

354

353

344

331

316

301

-286

271

256

242

229

216

186

162

141

123

75.8

21.8

0.00

1.38

5.63

7.14

9.49

13.8

22.2

37.2

57.6

77.5

91.9

101

108

112

115

117

118

119

120

121

122

122

123

124

124

125

125

126

129

0.00

5.78

23.6

29.9

39.7

57.7

93.0

156

241

325

385

425

451

468

480

489

495

500

504

507

510

512

514

518

520

522

524

529

542 ________ I A. .L I A. .5.

Radial enthalpy distribution and fuel enthalpy are presented at elevation 31.8 mm

Maximum value of fuel enthalpy is 84.7 cal/g fuel (t=3.88 s)

1) All numerical values are presented at elevation %ith peak po-r

H-80
#H18T !ndividu-Alatceristics ofRefabricaied Fuel Rods"

(Fresh F4A atdiated Cladding) under IGR Tests

Table H-5.5. Energy Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel

Rod #H18T

Energy Linear Energy of Clad-to-coolant heat

Tim deposition') power') Fuel enthalpy' metal-water Leakage of energy1 ) transfer coefficient'

(s) (cal/g fuel) (kW/m) (cal/g fuel) reaction') (cal/g fuel) (kW/m2K) (calle fuel)

____-_6 ____A__ FRAP-T6 FRAP-T6 FRAP-T6 SCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8.

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

1.56

6.37

8.08

10.7

15.6

25.1

42.1

652

87.7

104

115

122

126

130

132

134

135

136

137

138

138

139

140

140

141

141

143

0.00

5.42

12.6

17.8

29.7

57.6

113

181

210

171

115

74.2

48.8

33.3

23.6

17.3

13.1

10.3

8.27

6.78

5.53

4.68

3.99

2.79

2.12

1.67

1A0

0.93

0.00

1.43

5.50

6.96

9.27

13.6

22.2

37.1

56.2

72.6

81.5

84.5

842.

82.0

79.0

75.5

71.8

68.2

64.6

61.1

57.8

54.6

51.6

44.4

38.8

33.5

29.4

18.1

5.20

0.00

1.41

5.64

6.96

9.39

14.0

21.7

37.1

56.5

70.2

78.5

80.5

79.4

76.7

73.8

70.2

67.1

63.4

60.2

56.8

53.6

51.0

48.1

41.6

36.4

31.6

27.5

17.0

5.34

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.01

0.02

0.02

0.10

0.79

2.55

6.21

12.3

20.1

28.3

36.2

43.5

50.2

56.2

61.7

66.6

71.2

75A

79.3

82.9

86.2

93.9

99.9

105

0.00

0.00

0.04

0.06

0.08

0.30

1.17

3.46

8.31

14.9

24.3

33.7

41.8

49.6

55.6

61.9

66.7.

71.9

76.3

80.7

84.7

88.0

91.5

99.0

105

111

115

127

143

0.00 0.00

0.03

0.03

0.03

0.03

1.00

3.35

6.97

122

16.9

19.0

18.9

17.7

16.5

15.3

14.0

12.9

11.9

11.1

10.3

9.68

9.08

8.54

7.34

6.40

5.53

4.82

2.74

0.08

0.10

0.10

0.10

0.10

2.02

4.44

9.48

16.8

21.9

23.8

22.7

20.9

18.8

17.3

15.7

14.5

13A

12.5

11.6

10.8

10.2

9.58

8.21

7.12

6.11

5.24"

2.88

0.10

110

122

146 - 0.12 139

" Al nunerical values are presented at elevation %ith peak power

H-81
I :lndivid"a Chiai'.-A ofRefabricated Fuel Rods #H18T (Fresh Fuel, Preij Cladding) under IGR Test•s'.;':-' •,

Table H-5.6. Temperature Variation, Fission Gas Release and ZrO1 Thickness Vs. Time for Fuel

Rod #H18T Calculated by FRAP-T6 and SCANAIR Codes

Fuel centerline Fuel surface Clad outer Average (s) temperature'1 temperatureD temperature' thickness

(K) (K) (K)

FRAP-T6 SCANAIR FRAP-T6 SCANAIR FRAP-T6 SCANAIR FRAP-T6

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

320

391

415

452

521

654

•883

1183

1464

1657

1772

1832

1853

1846

1817

1771

1713

1646

1575

1502

.1429

1358

1189

1056

938

849

619

381

293

316

384

405

441

509

619

835

1119

1347

1535

1646

1698

1715

1705

1672

1631

1574

1514

1446

1378

1321

1255

1110

993

888

802

592

378

293

316

377

397

429

485

583

725

856

909

891

853

821

793

769

753

741

731

722

714

707

699

691

670

648

623

600

517

380

293

315

377

397

432

497

593

752

885

919

893

855

825

800

783

767

755

742

731

720

709

699

688

661

635

609

583

502

377

293

301

337

349

365

385

395

405

4i5

422

425

425

424

422

420

418

416

415

413

412

411

410

409

406

404

402

400

393

376

293

300

337

349

366

382

387

394

403

408

410

409

407

405

403

402

400

399

398

397

396

395

395

393

391

390

388

384

373

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

5

1) All nin ical values are presented at elevation with peak power

2) Initial ZrO2 thickness is 5 tun

H-82
#H18T lndividuai fhacteristics of Refabricated Fuel Rods" .(Fresh Fuet e-irrdiated Cladding) under IGR Tests

Table 11-5.7. Mechanical Characteristics of Fuel Rod #H18T Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes

Clad outer Fuel hoop Fuel - clad gap Clad hoop Clad hoop Internal gas Tim temperature') strain") width') strain") stress") pressure

(s) (K) 0%) (mm) (%) (MPa) (MPa)

FRAP-T61SCANAI1 FRAP.T61SCANAIR FRAP-T6JSCANAIRjFRAP.T6 SCANAIR FRAP-T6 SCANAIR FRAP-T6 SCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

301

337

349

365

385

395

405

415

422

425

425

424

422

420

418

416

415

413

412

411

410

409

406

404

402

400

393

376

293

300

337

349

366

382

387

394

403

408

410

409

407

405

403

402

400

399

398

397

396

395

395

393

391

390

388

384

373

0.00

0.02

0.09

0.11

0.15

0.21

0.34

0.57

0.88

1.18

1.37

1.47

1.49

1.48

1.44

1.39

1.33

1.26

1.19.

1.12

1.05

0.98

0.91

0.77

0.66

0.56

0A9

0.29

0.08

0.00 1 0.07 1 0.07 1 0.01 1 0.01 1 8.71

0.02 0.06 0.06 0.01 0.01 1 8.81

8.68

8.81

1.70

1.72

1.70

1.72

0.08 1 0.06 1 0.06 1 0.04 1 0.04 9.04 1 9.12 1 1.76 1 1.77

0.10

0.14

0.21

0.33

0.59

0.94

1.19

1.34

1.37

1.34

1.28

1.22

1.14

1.08

1.01

0.94

0.88

0.82

0.78

0.73

0.62

0.53

0.46

0.39

0.23

0.06

0.06

0.06

0.06

0.06

0.05

0.04

0.03

0.02

0.01

0.01

0.01

0.02

0.02

0.02

0.02

0.02

0.03

0.03

0.03

0.03

0.04

0.04

0.05

0.05

0.06

0.06

0.06

0.06

0.06

0.06

0.05

0.03

0.03

0.02

0.02

0.02

0.02

0.02

0.03

0.03

0.03

0.03

0.04

0.04

0.04

0.04

0.05

0.05

0.05

0.05

0.06

0.07

0.05

0.06

0.07

0.08

0.10

0.11

0.13

0.13

0.13

0.13

0.12

0.12

0.12

0.11

0.11

0.1i

0.11

0.10

0.10

0.10

0.10

0.09

0.09

0.09

0.08

0.06

0.05

0.06

0.08

0.08

0.10

0.12

0.14

0.14

0.14

0.13

0.13

0.12

0.12

0.11

0.11

0.11

0.11

0.10

0.10

0 .10

0.10

0.09

0.09

0.09

0.08

0.06

9.11

9.20

9.34

9.54

9.79

10.0

10.2

10.2

10.3

10.3

10.3

10.3

10.3

10.3

10.2

10.2

10.2

10.1

10.1

10.1

9.97

9.90

9.82

9.75

9.51

9.07

9.20

9.34

9.63

10.0

10.8

11.7

12.3

12.6

12.5

12.4

12.2

12.0

11.9

11.7

11.6

11.5

11.3

11.2

11.1

11.0

10.8

10.6

10.4

10.3

9.80

9.08

1.77

1.79

1.82

1.85

1.90

1.94

1.96

1.98

1.99

1.99

1.99

1.99

1.99

1.98

1.98

1.97

1.97

1.96

1.95

1.95

1:93

1.92

1.90

1.89

1.85

1.77

1.79

1.81

1.84

1.89

1.96

2.02

2.06

2.09

2.09

2.09

2.09

2.08

2.07

2.06

2.05

2.05

2.04

2.03

2.02

2.01

1.99

1.97

1.95

1.93

1.87

1.77

" All numerical values arc presented at elevation %ith peak powcr

H-83

.I--
#H18T Individual Chide cfs 6fRefabricated Fuel R6ds I(Fresh Fuel. Pleiirjr ladding) untder IGR Tests

Table H-5.8. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #H18T

Axial interval Ener deposition at infinite time Fuel enthalpy

from-to Erdot aifei at time (t=3.88 s)

(mm)-(mm) caVg fuel J/g fuel per-unit cal/g fuel J/g fuel per-unit

24.7-38.8 149 626 1.00 84.7 355 1.00

38.8 - 52.9 141 589 0.94 79.6 334 0.94

52.9-67.0 134 560 0.89 75.7 317 0.89

67.0-81.1 129 540 0.86 73.0 306 0.86

81.1 -95.2 127 532 0.85 71.9 301 0.85

95.2- 109.3 126 528 0.84 71.4 299 0.84

109.3 - 123.4 127 531 0.85 71.8 301 0.85

123.4- 137.5 128 535 0.85 72.4 303 0.85

137.5- 151.6 130 544 0.87 73.6 308 0.87

151.6 - 165.7 131 549 0.88 74.2 311 0.88

160

-- 140

120

• 100

2 80

60

S40

q 20

A

. . ... . ... ... . ... .. . ...

- Energy deposition

.... Fuel enthalpy

0

20 40 60 80 100 12

Axial coordinate (mm)

0 140 160 180

Fig. H-5.4. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6 Code

for Fuel Rod #H18T L

H-84
#H18T I I odividu ta - e ristics ofRefabiricated Fuel Rods ,":.

Fti 97(Fresh diated Cladding) under IGR Tests

1.2

0

* *1

0

0

t

1.0

0.8 -f0.6 -

0.4 -

V

IV

I1~ 2

2

I

I 3 4

Radial fuel coordinate (mm)

120

100

0

U

C.

C

w

80

60

40

20

0

U- l.Os

-- - 3.Os

-0- 3.9s

- -

1.0 1.5 2.0 2.5 3.0 3.5 4.0

Radial fuel coordinate (mm)

Fig. H-5.5. Radial Distributions of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #HI8T

H-85
#H18T hIndiiduaaflChiricetntM1 of Refabricated Fuel Rods -

-(Fresh Fuel,TPreira r Cladding) under IGR Tests

250 150

120

0

4-

0

5-

4)

0

0~

90

60

30

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

2000 25

E)

itC. U

4)

0

U

a0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. H-5.6. Energy and Temperature Characteristics Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes for Fuel Rod #H18T

H-86
#HI8T I I(Freshi lndivaduil'dtedstics FuIWti-rrdiated Cladding) of Refabricated under Fuel IGR Rods Tests:

2.4

2.0

1.6

1 .2

C;

E 0.8

0.4

0.0

0.16

0.12

•. 0.08

Cd

0.04

0.00

20

16

12

8 .

4

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

0.08

C.

CCCC

CC

U

U

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. H-5.7. Cladding Mechanical Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #H18T

H-87
#H18T :Individual C' "&'alc'fRefabricated Fuel Rod .

I(Fresh'Fuel; Preitk cCladding) under IGR Tes"s

2.0

1.6

1.2

C.L

0

0

• 0.8

0.4

0.0

2000

1600

1200

E

C.

400

0

0 1 .2 3 4 5 6 7 8 9 10

Time (s)

Fig. 11-5.8. Fuel Strain Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel Rod #1118T

H-88
#H18T I JadividuaE•Gharaeristics of Refabricated Fuel Rods* -

(Fresh Fu idiated Cladding) under IGR Tests

Table 11-5.9. Some Results of PIE for Fuel Rod #H18T

Characteristic Value -. J

1.

1.1.

1.2.

1.3.

1.4.

Measured parameters of cladding oxidation and cladding

deformation

Cladding thickness at elevation 90 mm for different azimuthal

angles (pm):

00

900

1800

2700

ZrO2 thickness at elevation 90 mm for different azimuthal angles

(pm):

00

900

1800

2700

ctZr(O) thickness at elevation 90 mm for different azimuthal angles

(pm):

00

900

1800

2700

Clad hoop strain at elevation 90 mm (%)

690

690

705

705

5

5

5

5

0

0

0

0

2.4 4

2.

2.1.

Measured parameters for FGR analysis

Internal gas composition (% by volume):

He

N2

02

Ar

CO2

Kr

Xe

Free gas volume (cm3)

Gas pressure inside fuel rod under normal condition (MPa)

Kr concentration in fuel (cm 3

/g fuel)

2.2.

2.3.

2.4.

6.1

1.735

3. Measured parameters of cladding hydriding

3.1. Coefficient of hydride orientation (per-unit) I:

3.2. Hydrogen concentration (% by weight)

H-89
#H18T 'individual -haraaoeibfRefabricated Fuel Rods" I(Fresh Fuil, Preirtl • .d'Iadding) under IGR Tests'.,'. -

Table H-5.10. General Characteristic of Fuel Rod #H18T

Parameter Unit Value

Experiment FRAP-T6 SCANAIR

1 Type of coolant - water water water

2 Burnup MWd/kg U 0 0 0

3 Energy deposition in fuel rod cal/g fuel 132 132 132

4 Peak fuel enthalpy caVg fuel - 85 81

5 Peak fuel temperature K - 1853 1715

6 Peak clad temperature K - 425 409

7 Fuel rod failure Yes, No No No -

8 Type of failure:

- cladding rupture due to ballooning Yes, No No No

- cladding rupture due to PCMI Yes, No No No

- fragmentation of fuel rod Yes, No No -

9 Failure time s - -

10 Fuel enthalpy at failure cal/g fuel - -

11 Outer cladding temperature at failure K -

12 Internal gas pressure at failure MPa - -

13 ZrO2 thickness after test Pm 5 5

14 Residual clad hoop strain: __" 

- peak value for ballooning area %-

- other location) % -2.4 0 0

"Calculated values by FRAP-T6 and SCANAIR codes are average along height or fuel rod excluding ballooning region

H-90
H-91

I .....
#B19T IndividuWlChlra sfRefabricated Ftuel Rods k .- I (Fresh Fuel, PreS'7ag .'q iadding) under IGR Tests'

Fig. H-6.1. Appearance of Fuel Rod #BI9T (photographs and X-ray photograph)

H-92
#B19T I dividu'Iý ristics of Refabricae Fuel Rods I(Fre6h , iated Cladding) un~derIGRTests -i

Position2

Position3

Fig. H-6.2. Cross-Section and Cladding Microstructure for Fuel Rod #BR9T at 35 mm Elevation

H-93
i ndividuad Ch-an&itte tcof q Refabricatcd Fuel Rc~ds #B19T (Freshi FtielAýOQiýi dii'ldding) under

Fig. H-6.3. Cross-Section and Cladding Microstructure for Fuel Rod #B19T at 90 mm Elevation

H-94
#B19T I FInditidi'frc iaiceo ladcdi Fuel Rods.

I (Fetht~t~5~~d4Mc Cladding) u-nder JRTs

Fig. H-6.4. Fuel Microstructure for Fuel Rod #B19T at 35 mm Elevation

H-95
#B19T S(Fr~esh Fuel, P.i•.M.• ,diaddmg) under IGR Tests ,•.

Table H-6.1. Time Dependent Energy Characteristics of Fuel Rod #B19T

Reactor Cumulative number of fissions Power of Energy deposition

Time energy in fuel rod (fiss) fuel rod in fuel rod

(s) deposi- U235 U238 Total ( cal/g fuel J/g fuel

tion_10_14) x xlO-1 xlO14 I (OX)III

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

9.0

10.0

20.0

30.0

0o

0.000

1.330

5.550

7.300

10.50

17.00

29.70

47.10

62.80

73.60

80.50

85.00

87.90

90.00

91.40

92.50

93.30

93.90

94.50

94.90

95.20

95.50

95.80

96.20

96.60

96.90

97.10

97.50

97.80

99.10

99.60

100.0

0.000

0.257

1.070

1.410

2.020

3.290

5.730

9.090

12.10

14.20

15.50

16.40

17.00

17.40

17.60

17.90

18.00

18.10

18.20

18.30

18.40

18.40

18.50

18.60

18.60

18.70

18.70

18.80

18.90

19.10

19.20

19.40

0.000

0.145

0.603

0.794

1.140

1.850

3.230

5.120

6.830

8.010

8.760

9.240

9.560

9.790

9.940

10.10

10.10

10.20

10.30

10.30

10.40

10.40

10.40

10.50

10.50

10.50

10.60

10.60

10.60

10.80

10.80

10.90

0.000

0.259

1.080

1.420

2.030

3.310

5.760

9.140

12.20

14.30

15.60

16.50

17.10

17.50

17.70

18.00

18.10

18.20

18.30

18.40

18.50

18.50

18.60

18.70

18.70

18.80

18.80

18.90

19.00

19.20

19.30

19.50

0.000

1.450

3.800

6.100

11.90

25.30

43.30

48.20

36.20

23.60

15.10

9.890

6.730

4.760

3.500

2.660

2.080

1.670

1.370

1.130

0.966

0.832

0.723

0.532

0.416

0.341

0.291

0.250

0.202

0.053

0.028

0.000

0.000

2.940

12.20

16.10

23.10

37.60

65.60

104.0

139.0

163.0

178.0

188.0

195.0

199.0

202.0

205.0

207.0

208.0

210.0

211.0

211.0

212.0

213.0

214.0

215.0

216.0

216.0

218.0

218.0

223.0

224.0

229.0

0.000

12.30

51.10

67.40

96.70

157.0

275.0

435.0

582.0

682.0

745.0

787.0

816.0

833.0

846.0

858.0

867.0

871.0

879.0

883.0

883.0

887.0

892.0

896.0

900.0

904.0

904.0

913.0

913.0

.933.0

938.0

959.0

Maximum value of power is 49.1 kW (t - 2.95 s)

I) Current energy deposition per maximum energy deposition (at infimite time)

H-96

I ...
#B19T ,t'j-D amcter d RefabrinaiitdI Fuel Rods

IM !t.s~~j Cladding) un~der IGR TestsX','

Table H-6.2 Axial Energy Characteristics of Fuel Rod #B19T

Axial Cumulative number of fissions Maximum Energy deposition

coordinate at axial interval (fiss) power of at infinite time*

from lower U235 U238 Total fuel rod cal/g fuel J/g fuel per-unit3)

end of fuel (W)

rod x10" xl0" xl0"13 t=2.95 s

(mm)

15.0'

20.0O'

25.0

30.0

35.0

40.0

45.0

50.0

55.0

60.0

65.0

70.0

75.0

80.0

85.0

90.0

95.0

100.0

105.0

110.0

115.0

120.0

125.0

130.0

135.0

140.0

145.0

150.0

155.0

160.02)

165.0

0.000

4.670

7.410

7.320

7.220

7.130

7.030

6.970

6.910

6.860

6.840

6.900

6.860

6.770

6.710

6.740

6.780

6.780

6.780

6.770

6.850

6.850

6.790

6.740

6.730

6.670

6.650

6.620

6.630

3.800

0.000

0.000

2.270

3.680

3.700

3.730

3.760

3.760

3.790

3.810

3.840

3.860

3.930

3.950

3.920

3.910

3.950

3.980

3.990

3.990

3.990

4.040

4.030

3.990

3.950

3.930

3.870

3.840

3.800

3.780

2.160

0.000

0.000

4.690

7.440

7.360

7.250

7.170

7.070

7.010

6.950

6.900

6.880

6.940

6.900

6.810

6.750

6.780

6.820

6.820

6.820

6.810

6.890

6.890

6.830

6.780

6.770

6.710

6.690

6.660

6.660

3.820

0.000

0.000

1.180

1.870

1.850

1.830

1.800

1.780

1.760

1.750

1.740

1.730

1.750

1.740

1.710

1.700

1.710

1.720

1.720

1.720

1.710

1.730

1.730

1.720

1.710

1.700

1.690

1.680

1.680

1.680

0.962

0.000

0.000

251.0

247.0

244.0

240.0

237.0

235.0

233.0

231.0

230.0

228.0

228.0

227.0

227.0

226.0

226.0

226.0

225.0

225.0

225.0

226.0

225.0

224.0

225.0

224.0

224.0

223.0

221.0

221.0

219.0

0.000

0.000

1051.

1034.

1021.

1005.

992.0

984.0

975.0

967.0

963.0

954.0

954.0

950.0

950.0

946.0

946.0

946.0

942.0

942.0

942.0

946.0

942.0

938.0

942.0

938.0

938.0

933.0

925.0

925.0

917.0

0.000

0.00

1.00

0.98

0.97

0.96

0.94

0.94

0.93

0.92

0.92

0.91

0.91

0.90

0.90

0.90

0.90

0.90

0.90

0.90

0.90

0.90

0.90

0.89

0.90

0.89

0.89

0.89

0.88

0.88

0.87

0.00

All numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate ± 2.5 mm.

1) Initial coordinate of fuel is 19.4 nmm.

2) End coordinate of fuel is 160.4 nun.

3) Current value per maximum value.

H-97
#B19T. Initidividual Char o~fRefabricated Fuel Rods- I (Fresh Fuel. Preir~ ICladding) under IGR Tests

Table H-6.3. Radial Energy Characteristics of Fuel Rod #B19T

Coordinates of fuel zones (mm)

Characteristics* I zone 2 zone 3 zone 4 zone

1.10-2.12 2.12 -2.79 2.79-3.32 3.32-3.79

Number of fissions x 104 4 (fiss) 4.680 4.760 4.890 5.050

Power of fuel rod') (kW) 11.80 12.00 12.30 12.70

U235 Energy deposition 2

) (cal/g fuel) 220.0 224.0 230.0 237.0

Energy deposition 2

) (J/g fuel) 921.0 938.0 963.0 992.0

Energy deposition3

) (per-unit) 0.928 0.945 0.970 1.000

Number of fissions x10"-2 (fiss) 2.750 2.730 2.720 2.730

Power of fuel rod') (kW) 0.068 0.068 0.068 0.068

U238 Energy deposition2

) (cal/g fuel) 1.270 1.260 1.260 1.260

Energy deposition2

) (J/g fuel) 5.320 5.270 5.270 5.270

Energy deposition3

) (per-unit) 1.000 0.992 0.992 0.992

Number of fissions x10"14 (fiss) 4.710 4.780 4.910 5.080

Power of fuel rod') (kW) 11.90 12.00 12.40 12.80

Total Energy deposition 2

) (cal/g fuel) 221.0 225.0 231.0 239.0

Energy deposition2

O (J/g fuel) 925.0 942.0 967.0 1000.

Energy deposition 3

) (per-unit) 0.925 0.941 0.967 1.000

1) at time or3.65 s, 2) at infinite time, 3) Current value per maximum value

All numerical values of characteristics were calculated for length of fuel stack

H-98
#B19T I lndividua [ tristicsof Refabricated Fuel Rods:'

r(FrehF idae Cladding) under IGR Tests

Table 11-6.4. Fuel Enthalpy Vs. Time Calculated by FRAP-T6 Code for Fuel Rod #B19T

Enthalpy at fuel radius 1 Energy deposition Time (cal/ fuel) ,Fuel enthalpy ___ ' in fuel rod

(s) 1.10mm I 2.22 mm 2.89nmm 3.79mn calg fuel JIg fuel cal/g fuel J/g fuel

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

42

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

2.71

11.5

15.3

22.2

36.9

65.8

107

145

172

190

201

207

211

213

214

214

213

213

211

211

207

207

204

200

196

192

179

113

0.00

2.69

11.3

15.1

22.0

36.7

65.6

106

144

169

185

194

199

202

203

204

204

203

203

201

201

198

198

195

191

188

185

174

112

0.00

2.63

10.9

14.5

21.3

35.7

64.0

103

136

156

169

178

183

185

187

187

187

187

187

186

186

184

184

182

179

177

175

166

110

0.00

2.35

9.56

12.6

18.2

29.3

48.0

67.3

80.6

116

136

145

149

153

155

157

159

160

160

161

161

161

161

160

159

158

157

151

105

0.00

2.61

10.9

14.5

21.1

35.2

62.3

99.0

130

153

170

179

185

188

190

190

191

190

190

189

189

187

187

185

182

180

177

167

110

0.00

10.9

45.6

60.6

88.4

147

261

415

.546

643

711

752

774

787

794

798

799

798

798

794

794

785

785

774

763

752

741

701

461

0.00

2.94

12.2

16.1

23.1

37.6

65.5

104

139

163

178

188

195

199

202

205

207

208

208

211

211

212

212

214

215

216

216

218

224

0.00

12.3

51.3

67.6

96.8

158

275

435

581

681

746

787

815

834

848

859

867

873

873

882

882

890

890

896

900

903

906

915

939

Radial enthalpy distribution and fuel enthalpy are presented at elevation 26.4 mm

Maximnum value of fuel enthalpy is 190.6 caig fuel (t=4.84 s)

1) All numraical values are presented at elevation with peak power

H-99
#B19T Individual Chaetscts• ofiRefabricated Fuel Rods'. -

(Freshi Futel, Preiri - __Cladding) under IGR Testsi

Table 11-6.5. Energy Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel

Rod #1B19T

1Energy Linear Clad-to-coolant heat (s)e deposition"~ poivr) Fuel enthalpy Leakage of energy) transfer coefficienti)

(s) (cal/g fuel) (kW/m) (calg fuel) (cal/g fuel) (kW/m2K)

FRAP-T6I SCANAIR FRAP-T6 ISCANAIR FRAP-T6 SCANAIR

0.0

1.0

2.0

22

2A

2.6

2.8

3.0

32

3A

3.6

3.8

4.0

4.2

4A

4.6

4.8

5.0

52

5A

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

3.16

13.2

17.3

24.8

40.4

70.5

112

149

175

191

202

209

214

218

220

222

224

224

226

226

229

229

230

231

232

233

235

241

0.00

10.9

28.7

46.0

89.8

191

327

364

273

178

114

74.7

50.8

35.9

26A

20.1

15.7

12.6

12.6

8.52

8.52

5.84

5.84

4.25

3.28

2.67

2.26

1.56

0.21

0.00

2.61

10.9

14.5

21.1

35.2

62.3

99.0

130

153

170

179

185

188

190

190

191

190

190

189

189

187

187

185

182

180

177

167

110

0.00

2.83

11.3

14.8

21.4

35.1

61.4

96.2

0.00

0.00

0.01

0.01

0.01

0.02

0.03

0.07

0.16

0A0

0.74

1.16

1.66.

2.27

2.98

3.78

4.65

5.60

5.60

7.68

7.68

10.6

10.6

13.8

17.1

20.6

24.1

38.1

128

0.00

0.00

0.01

0.01

0.02

0.02

0.04

0.10

0.00

0.01

0.01

0.01

0.01

0.01

0.02

0.03

0.05

0.08

0.08

0.10

0.11

0.12

0.13

0.14

0.15

0.16

0.16

0.17

0.17

0.18

0.18

0.19

0.20

0.20

0.20

0.20

0.11

0.00

0.01

0.01

0.01

0.01

0.02

0.02

0.04

1) All numirical values ar' presented at elevation s~th peak pol er

H-100
#~B19T .landing) niv racferst-cs of RefabriCated nder Fuel' Rods: . (Fres Fue.i'•.Irra.diated Cladding) under IGR Tests ., 'I

Table 11-6.6. Temperature Variation, Fission Gas Release and ZrO2 Thickness Vs. Time for Fuel

Rod #B19T Calculated by FRAP-T6 and SCANAIR Codes

Time Fuel centerline Fuel surface Clad outer ) I) (s) temperature') temperature ) temperature )

(___(K) F (K) (K)

FRAP-T6 ISCANAIR FR4-6 SCANAIR FRAP-T6 ISCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

340

478

534

634

838

1222

1737

2167

2430

2581

2668

2717

2744

2757

2763

2762

2758

2758

2743

2743

2717

2717

2688

2658

2628

2599

2494

1815

293

338

471

523

616

802

1144

1593

293

334

449

495

576

733

987

1241

1412

1852

2073

2165

2210

2246

2273

2294

2310

2320

2320

2327

2327

2327

2327

2321

2313

2302

2290

2234

1721

293

337

457,

, 506

593

764

1048

1357

293

305

369

393

428

491

618

847

1120

1297

1357

1433

1512

1580

1636

1683

1721

1753

1753

1808

1808

1857

1857

1891.

1912

1924

1929

1912

1518

293

308

381

409

451

530

687

946

H-101
#B19T Inividual Ch "acei•-fRefabricated Fuel Rods

(Fresh Fuel,'Pieiri• Cladding) under IGR Tests

Table 11-6.7. Mechanical Characteristics of Fuel Rod #B19T Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes

Clad outer Fuel hoop Fuel - clad gap Clad hoop Clad hoop Internal gas Time temperaturet) strain') width') straini) stress') pressure

(S) (K) (%) (mm) (%) (MPa) (MPa)

FRAP-T6 SCANAIR FRAP-T6 SCANAIR FRAP-T61SCANAIR FRAP-T61SCANAIR FRAP-T6TSCANAIR FRAP-T6 SCANAIF

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

305

369

393

428

491

618

847

1120

1297

1357

1433

1512

1580

1636

1683

1721

1753

1753

1808

1808

1857

1857'

1891

1912

1924

1929

1912

1518

293

308

381

409

451

.530

687

946

0.00

0.04

0.17

0.23

0.33

0.53

0.96

1.59

2.14

2.49

2.71

2.83

2.89

2.93

2.95

2.96

2.96

2.96

2.96

2.94

2.94

2.91

2.91

2.88

2.84

2.80

2.77

2.64

1.74

0.00

0.03

0.13

0.17

0.25

0.42

0.80

1.36

0.08

0.07

0.07

0.07

0.07

0.06

0.05

0.03

0.02

2.72

2.71

2.71

2.71

2.70

2.70

2.70

2.70

2.70

2.70

2.70

2.70

2.71

2.71

2.71

2.71

2.71

2.71

2.72

2.75

0.08

0.07

0.07

0.07

0.07

0.07

0.06

0.04

0.01

0.02

0.06

0.08

0.10

0.15

0.24

0.39

0.55

66.3

66.3

66.4

66.5

66.6

66.6

66.7

66.7

66.7

66.7

66.8

66.8

66.8

66.8

66.9

66.9

66.9

66.9

66.9

66.5

0.01

0.02

0.08

0.10

0.13

0.19

0.32

0.52

8.72

8.90

9.28

9.39

9.55

9.79

10.1

10.3

10.5

0.00

0.00

0.00

0.00

0.00

0.00

0.00

.0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

8.69

8.91

9.34

9.47

9.66

9.96

10.3

10.5

1.70

1.73

1.80

1.82

1.85

1.89

1.95

1.99

2.02

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

1.70

1.74

1.81

1.83

1.86

1.89

1.94

1.97

'All numerical values arc presented at elevation with peak po1%vr

H-102
#B19T i :lndividhual acterdstics of Refabricited Fuel Rods

jIFr•sh Fuel' rY rradiated Cladding) under IGR Tests

Table 11-6.8. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #B19T

Axial interval Energy deposition at infinite time Fuel enthalpy

from-to at time (t=4.84 s)

(mm)-(mm) cal/g fuel J/g fuel per-unit cal/g fuel Jig fuel per-unit

19.4-33.5 246 1031 1.00 191 799 1.00

33.5 -47.6 237 993 0.96 184 769 0.96

47.6-61.7 231 970 0.94 179 751 0.94

61.7-75.8 228 955 0.93 176 739 0.93

75.8 - 89.9 226 949 0.92 175 735 0.92

89.9-104.0 226 945 0.92 175 732 0.92

104.0 - 118.1 225 944 0.92 174 731 0.92

118.1 - 132.2 225 941 0.91 174 729 0.91

132.2- 146.3 224 938 0.91 173 726 0.91

146.3 - 160.4 221 925 0.90 171 716 0.90

250

200

"4 150

- 100

50

S .7

Energy deposition

... Fuel enthalpy

.

0

0 30 60 90

Axial coordinate (mm)

120 150 180

Fig. H-6.5. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6 Code

for Fuel Rod #B19T

H-103

I _
#B19T Individual Charcn-c of Refabricated Fuel Rodsi,:,

, (Frsh Fue'l. PreihTAAi& Cladding) undei IGR Tests

1.2

0

1.0

0.8

0.6

0.4

I.

0.2

.1I 2 3 4

Radial fuel coordinate (mm)

250

200

I~2.OsI I~3.OsI

cc

03

1-5--

100-

50 __________

n -_____ 3 - -

1.0 1.5 2.0 2.5 3.0 3.5 4.0

Radial fuel coordinate (mm)

Fig. H-6.6. Radial Distributions of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #B19T

H-104
#B19T I lndividuarfl"-aratenstlcs of Refabricated Fuel Rods'

I(Fresh Ftietrerrdiited Cladding) under IGR Test

400

350

300

250

200

0

150

O0

100

50

0

3000

2500

2000

1500

1000

500

-240

210

180

150

120 .

90 U

00

6.0

30

0

0.30

0 1 2 3 4 5 6 .7 8 9 10

Time (s)

0.25

0.20

0.15

0.10

L=

0

U

0.05

0.00

0 1 2 3 4 5 '6 7 8 9 10

Time (s)

Fig. H-6.7. Energy and Temperature Characteristics Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes for Fuel Rod #B19T

H-105
#B19T 'Individual Ciaramtin s~ ofRefabricated Fuel Rods.

'(Fresh Fuel, Priirrif = Cladding) under IGR Tests

2.5

E)

15

12

,a

0

6 ="

3

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

0.

0•

0

.0

*0

100

80

60

40

20

0

-0--

FRAP-T6 .... SCANAIR

--- Clad hoop strain

- Fuel-clad gap width

3.0

2.4

E

1.8

*0

Cw

*0

1.2 .c

0.6

0.0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. H-6.8. Cladding Mechanical Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #B19T

H-106
#B19T ndivdual i ctenstics of Refabricated Fuel Rods

(Frsh Fue Tadiated Cladding) under IGR Tests

0

0.

3.0

2.5

2.0

1.5

1.0

0.5

0.0

3000

2500

2000

1500

1000

500

0

Li

0.

E

Li

Li

Li

Li

U

Li

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. H-6.9. Fuel Strain Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel Rod #B19T

H-107
#B19T Individual Chiractin s-ofRefabricaied Fuel Rods

(F7resh Fuel, Pmekr 2

ý~ Cladding) under' JOR Tests

Table H-6.9. Some Results of PIE for Fuel Rod #B19T

Characteristic Value

1. Measured parameters of cladding oxidation and cladding

deformation

1.1. Cladding thickness at elevation 90,35 mm correspondent to

different azimuthal angles (pm):

00 663 600

900 677 R

1800 634 545

2700 606 590

1.2. ZrO2 thickness at elevation 90, 35 mm correspondent to different

azimuthal angles (pm):

00 30 30

900 40 -

1800 30 40

2700 25 30

1.3. ctZr(O) thickness at elevation 90, 35 mm correspondent to different

azimuthal angles (pm):

00 25 40

900 40 -

1800 25 45

2700 25 40

1.4. Clad hoop strain at elevation 90, 35 mm, respectively (%) 8.9 32.8

2. Measured parameters for FGR analysis

2.1. Internal gas composition (% by volume):

He

N2

02"

Ar

C02

Kr -

Xe

2.2. Free gas volume (cm3)

2.3. Gas pressure inside fuel rod under normal condition (MPa)

2.4. Kr concentration in fuel (cm3

/g fuel)

3. Measured parameters of cladding hydriding

3.1. Coefficient of hydride orientation (per-unit)

3.2. Hydrogen concentration (% by weight)

H-108
#B19T Mndividuwlih cteristics of Refabricated Fuel Rods I (Fresh Fue•V e!"ffdiated Cladding) under IGR T est' 2 + i.

Table 11-6.10. General Characteristic of Fuel Rod #B19T

Parameter Unit Value

___Experiment FRAP-T6 SCANAIR

I Type of coolant air air air

2 Burnup MWd/kg U 0 0 0

3 Energy deposition in fuel rod cal/g fuel 229 229 229

4 Peak fuel enthalpy cal/g fuel - 191 -

5 Peak fuel temperature K - 2763 -

6 Peak clad temperature K 1929 -

7 Fuel rod failure Yes, No Yes Yes -

8 Type of failure:

- cladding rupture due to ballooning Yes, No Yes Yes -

- cladding rupture due to PCMI Yes, No No No -

- fragmentation of fuel rod Yes, No No - -

9 Failure time s - 3.34 -

10 Fuel enthalpy at failure cal/g fuel - 147 -

11 Outer cladding temperature at failure K - 1286 -

12 Internal gas pressure at failure MPa - 2.01 -

13 ZrO2 thickness after test pm 25-40 - -

14 Residual clad hoop strain:

- peak value for ballooning area % 32.8 65.96 -

- other location 1) % 8.9 0.74 -

')Calculated values by FRAP-T6 and SCANAIR codes are average along height of fuel rod excluding ballooning region

H-109

INL

H-111
#B20T Individu&W CharA"rlst? tf Refabricated Fuel Rods'.'.

(Frsh Peir ue, cddig)unideri IGR .Tests*_', -ý

PositionW (900)

I

Fig. H-7.1. Appearance of Fuel Rod #B20T (photographs and X-ray photograph)

H-112

I ___ -
#B2OT I' ~dvidi~E~~ t

eistcsofRefabricated FuelRds

(ie ia~ Cladding) underIRTet

Pnditinn 1

Fig. H-7.2. Cross-Section and Cladding Microstructure for Fuel Rod #B20T at 30 mm and 80 mm

Elevations '

H-113
#B20T I fn~~nd~iv~~idual Char~~~~f;ReR abric~ate Fuel Rods " "(FrFmh Feli••I j i addg) under I GR Tests .

Position I

--a

Position2

Fig. H-7.3. Fuel Microstructure for Fuel Rod #BMOT at 30 mm Elevation

H-114

I ---
#B20T IJndi:Ycia--lW-MMMC1ist s of Refabricae Fuel Rods

(FehF ~ MO, ated Cladding) ude Ir IGR.Tst ITtstsg

Table 11-7.1. Time Dependent Energy Characteristics of Fuel Rod #B20T

Reactor Cumulative number of fissions Power of Energy deposition

Time energy in fuel rod (fiss) fuel rod in fuel rod

(s) deposi- 235 23cag fuel

tion U U23 Total (kW) ue J/g fuel int) xl04 x1012 x1014

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

9.0

10.0

20.0

30.0

0o

0.000

0.515

2.060

2.490

2.970

3.480

4.040

4.640

5.340

6.190

7.300

8.910

11.50

16.00

24.00

36.90

53.20

68.10

78.30

84.40

87.90

90.00

91.40

93.50

94.80

95.70

96.30

97.10

97.70

99.30

99.80

101.0

0.000

0.070

0.281

0.340

0.405

0.475

0.551

0.635

0.730

0.846

0.998

1.220

1.570

2.190

3.280

5.040

7.270

9.300

10.70

11.50

12.00

12.30

12.50

12.80

13.00

13.10

13.20

13.30

13.30

13.60

13.60

13.80

0.000

0.040

0.158

0.192

0.228

0.268

0.310

0.357

0.411

0.476

0.562

0.685

0.883

1.230

1.850

2.840

4.090

5.240

6.030

6.490

6.760

6.920

7.030

7.190

7.290

7.360

7.400

7.470

7.510

7.640

7.680

7.750

0.000

0.071

0.283

0.342

0.408

0.478

0.555

0.638

0.735

0.851

1.000

1.220

1.580

2.200

3.300

5.070

7.310

9.360

10.80

11.60

12.10

12.40

12.60

12.90

13.00

13.20

13.20

13.30

13.4o

13.70

13.70

13.80

0.000

0.397

0.796

0.876

0.956

1.040

1.120

1.250

1.470

1.840

2.520

3.820

6.420

11.50

20.00

29.30

31.90

24.70

15.30

8.820

5.220

3.350

2.340

1.310

0.920

0.613

0.433

0.323

0.212

0.042

0.021

0.000

0.000

0.797

3.190

3.860

4.600

5.400

6.270

7.210

8.300

9.620

11.30

13.80

17.80

24.80

37.30

57.20

82.40

106.0

122.0

131.0

137.0

140.0

142.0

146.0

148.0

149.0

150.0

152.0

153.0

156.0

158.0

161.0

0.000

3.340

13.40

16.20

19.30

22.60

26.20

30.20

34.70

40.30

47.30

57.80

74.50

104.0

156.0

239.0

345.0

444.0

511.0

548.0

573.0

586.0

594.0

611.0

620.0

624.0

628.0

636.0

640.0

653.0

661.0

674.0

Maximum value of power is 32.3 kW (t - 4.75 s)

1) Current energy deposition per maximum energy deposition (at infinite time)

H-1I5
#B2OT -11ridiv'Idii dia7 Ch ricm~fbiae s Fe ~~~ (Fes F e7P~ Cld~adding) unlRfTests:..-

Table H-7.2. Axial Energy Characteristics of Fuel Rod #B20T

Axial Cumulative number of fissions Maximum Energy deposition

coordinate at axial interval (fiss) power of at infinite time*

from lower u235 u235 Total fuel rod cal/g fuel J/g fuel per-unit3)

end of fuel x10-" XlO" Xi0-1 3 (kW)

rod xlo'n xlO'3 tlO'_--4.75 s (mm)

20.0

25.0')

30.0

35.0

40.0

45.0

50.0

55.0

60.0

65.0

70.0

75.0

80.0

85.0

90.0

95.0

100.0

105.0

110.0

115.0

120.0

125.0

130.0

135.0

140.0

145.0

150.0

155.0

160.0

165.02)

170.0

0.000

4.770

5.200

5.150

5.060

5.010

4.910

4.870

4.930

4.900

4.830

4.730

4.720

4.760

4.760

4.770

4.800

4.770

4.730

4.730

4.730

4.730

4.720

4.690

4.680

4.610

4.590

4.630

4.660

3.210

0.000

0.000

2.310

2.590

2.610

2.630

2.640

2.630

2.650

2.720

2.730

2.730

2.700

2.710

2.760

2.770

2.790

2.820

2.810

2.790

2.790

2.790

2.780

2.770

2.740

2.730

2.680

2.650

2.660

2.660

1.820

0.000

0.000

4.790

5.220

5.180

5.090

5.030

4.930

4.890

4.950

4.920

4.860

4.760

4.740

4.790

4.790

4.800

4.830

4.800

4.760

4.760

4.760

4.750

4.750

4.710

4.700

4.630

4.620

4.660

4.690

3.230

0.000

0.000

1.120

1.220

1.210

1.190

1.170

1.150

1.140

1.150

1.150

1.130

1.110

1.110

1.120

1.120

1.120

1.130

1.120

1.110

1.110

1.110

1.110

1.110

1.100

1.100

1.080

1.080

1.090

1.090

0.752

0.000

0.000

176.0

173.0

171.0

168.0

167.0

165.0

164.0

163.0

162.0

161.0

160.0

159.0

160.0

160.0

159.0

159.0

159.0

158.0

158.0

158.0

158.0

159.0

158.0

158.0

157.0

157.0

156.0

155.0

154.0

0.000

0.000

737.0

724.0

716.0

703.0

699.0

691.0

687.0

682.0

678.0

674.0

670.0

666.0

670.0

670.0

666.0

666.0

666.0

661.0

661.0

661.0

661.0

666.0

661.0

661.0

657.0

657.0

653.0

649.0

645.0

0.000

0.00

1.00

0.98

0.97

0.95

0.95

0.94

0.93

0.93

0.92

0.91

0.91

0.90

0.91

0.91

0.90

0.90

0.90

0.90

0.90

0.90

0.90

0.90

0.90

0.90

0.89

0.89

0.89

0.88

0.88

0.00

* All numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate ± 2.5 nun.

1) Initial coordinate of fuel is 23.0 nun.

2) End coordinate of fuel is 166.0 nun.

3) Current value per maximum value.

H-116

I - -
M~BOT I 1 dF~d eti1~htics of Refkl~i46te Fu"el Ios

,[(Ri Wriaed Clidding) underIGR ,Tests'

Table 11-7.3. Radial Energy Characteristics of Fuel Rod OB20T

Coordinates of fuel zones (mm)

Characteristics* I zone 2 zone 3 zone 4 zone

1.10-2.12 2.12-2.79 2.79-3.32 3.32-3.79

Number of fissions x10"14 (fiss) 3.330 3.380 3.470 3.590

Power of fuel rod') (kW) 7.750 7.870 8.090 8.370

U23s Energy deposition2 ) (caVg fuel) 155.0 157.0 162.0 167.0

Energy deposition2 ) (J/g fuel) 649.0 657.0 678.0 699.0

Energy deposition3) (per-unit) 0.928 0.940 0.970 1.000

Number of fissions xI0"12 (fiss) 1.950 1.930 1.930 1.930

Power of fuel rod') (kW) 0.045 0.045 0.044 0.045

U238 Energy deposition2 ) (caVg fuel) 0.895 0.889 0.887 0.889

Energy deposition2 ) (J/g fuel) 3.750 3.720 3.710 3.720

Energy deposition3) (per-unit) 1.000 0.993 0.991 0.993

Number of fissions x 10-14 (fiss) 3.340 3.400 3.490 3.610

Power of fuel rod') (kW) 7.800 7.920 8.130 8.410

Total Energy deposition2 ) (cal/g fuel) 156.0 158.0 162.0 168.0

Energy deposition2 ) (J/g fuel) 653.0 661.0 678.0 703.0

Energy deposition3) (per-unit) 0.929 0.940 0.964 1.000 2) 3)

I) at time of 4.75 s, 2) at infinite time, Current value per maximum value

* All numerical values of characteristics ,ere calculated for length of fuel stack

H-117

I -
#B2OT l individuali Ch'aia8CM"!Nrvaof Refabricated Fuel Rods

:(Fresh Fuel, Preir•ia Cladding) under IGR Tests .

Table 11-7.4. Fuel Enthalpy Vs. Time Calculated by FRAP-T6 Code for Fuel Rod #B2OT

Enthalpy at fuel radius Energy deposition

Time _(cal/~ fuel Fuel I in fuel rod

(S) 1.10mm 2.22 mm 2.89 mm 3.79 mm ca/g fuel I ig fuel cawg fuel Jig fuel

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4A

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

0.73

2.84

3.43

4.08

4.78

5.55

6.38

7.35

8.55

10.1

12.5

16.4

23.4

36.0

56.4

82.8

107

124

134

139

142

142

141

138

135

133

125

89.2

0.00

0.72

2.80

3.38

4.01

4.70

5.45

6.27

7.23

8.40

9.98

12.3

16.2

23.2

35.7

56.1

82.2

106

122

130

134

134

134

133

131

130

128

122

88.4

0.00

0.71

2.71

3.27

3.88

4.55

5.27

6.06

6.99

8.13

9.66

11.9

15.7

22.5

34.8

54.5

79.2

101

113

118

119

119

121

122

122

122

121

118

87.1

0.00

0.64

2.47

2.98

3.54

4.15

4.81

5.53

6.37

7.40

8.77

10.8

14.0

19.6

29.1

42.8

57.4

68.6

75.5

78.6

91.2

100.0

104

108

109

110

111

111

84.8

0.00

0.70

2.71

3.27

3.89

4.56

5.28

6.08

7.00

8.14

9.67

11.9

15.7

22.4

34.3

53.4

77.1

97.8

111

117

120

123

124

125

125

124

123

119

87.4

0.00

2.95

11.4

13.7

16.3

19.1

22.1

25.5

29.3

34.1

40.5

50.0

65.7

93.7

144

224

323

410

464

489

503

515

521

525

524

520

515

498

366

0.00

0.80

3.19

3.86

4.60

5.40

6.27

7.21

8.30

9.62

11.3

13.8

17.8

24.8

37.3

57.2

82.4

106

122

131

136

140

142

146

148

149

150

153

158

0.00

3.34

13A

16.2

19.3

22.6

26.3

30.2

34.8

40.3

47.5

57.9

74.7

104

156

240

345

442

509

549

572

586

595

610

619

625

630

641

660

Radial enthalpy distribution and fuel enthalpy are presented at elevation 30.1 mm

Maxin=m value of fuel enthalpy is 125.3 camg fuel (t=6.51 s)

" All numerical values are presented at elevation with peak po',cr

H-118
#B2OT IIndividui4[:ifticristics of Refabricaled Fuel Rods .

(Fresh FxiA -iadiated Cladding) under IGR Tests

Table H-7.5. Energy Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel

Rod #B20T

e Energy Linear Clad-to-coolant heat

Time depo ' 1 Fuel enthalpyW Leakage of energy' transfer coefficient' (s) (cal/g fuel) (kW/m) (ca(g fuel) (cal/g; fuel) (kW/miK)

FRAP-T6 SCANAIR F1AP-T6 ISCANAIR FRAP-T6 ISCANMR

0.0

1.0

2.0

2.2

2A

2.6

2.8

3.0

32

3A

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

0.86

3.43

4.15

4.94

5.80

6.73

7.74

8.91

10.3

12.2

14.8

19.1

26.6

40.0

61.4

88.5

113

130

141

146

150

153

156

159

160

161

164

169

0.00

2.96

5.93

6.53

7.13

7.75

8.35

9.32

11.0

13.7

18.8

28.5

47.9

85.7

149

218

238

184

114

65.8

38.9

25.0

17.4

9.77

6.86

4.57

3.23

1.58

0.15

0.00

0.70

2.71

3.27

3.89

4.56

5.28

6.08

7.00

8.14

9.67

11.9

15.7

22.4

34.3

53.4

77.1

97.8

111

117

120

123

124

125

125

124

123

119

87.4

0.00 0.00

0.77

2.95

3.55

4.19

4.89

5.65

6.47

7.42

8.58

10.1

12.4

16.1

22.7

34.4

53.0

75.8

95.5

0.00

0.00

0.00

0.00

0.00

0.00

0.01

0.01

0.01

0.01

0.02

0.02

0.02

0.03

0.05

0.07

0.13

0.24

0.40

.0.62

0.90

1.20

2.07

3.10

4.28

5.58

11.4

58.6

0.00

0.00

0.00

0.00

0.00

0.00

0.01

0.01

0.01

0.01

0.01

0.02

0.02

0.03

0.04

0.06

0.10

0.18

0.00

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.02

0.03

0.04

0.05

0.06

0.07

0.08

0.08

0.09

0.10

0.11

0.11

0.12

0.08

0.00

0.01

0.01

0.01'

0.01

0.01

0.01

0.01

0.01.

0.01

0.01

0.01

0.01

0.01

0.02

0.02

0.03

0.05

1) All numerical values are presented at elevation with peak powcr

H-I 19
#B2OT Individufi ChaIe~r'aIst k fRcfabricated Fuel Rods

I(Fresh Fuel, Pre•i;T•.• ladding) under IGR Tests.

Table 11-7.6. Temperature Variation, Fission Gas Release and ZrO2 Thickness Vs. Time for Fuel

Rod OB20T Calculated by FRAP-T6 and SCANAIR Codes

Fuel centerline Fuel surface Clad outer Time temperature') temperature') temperaturel)

(s) (K) (K) (K)

FRAP-T6 SCANAIR SFlA-T6 SCANAIR WAP-T6 I'SCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

306

342

352

363

374

386

399

415

433

457

493

550

650

825

1099

1440

1745

1946

2056

2111

2136

2143

2125

2097

2068

2041

1952

1521

293

306

341

351

361

372

384

397

412

430

453

487

541

633

793

1039

1339

1606

293

305

336

344

354

364

374

386

399

415

437

467

515

597

730

917

1112

1259

1347

1386

1546

1655

1700

1749

1770

1781

1788

1785

1465

293

305

338

347.

357

367

378

390,

404

421

443

475

526

613

757

963

1182

1350

293

296

313

318

324

331

339

347

356

367

380

395

417

450

507

606

760

948

1089

1183

1281

1303

1332

1402

1462

1508

1541

1591

1355

293

297

315

321

328

336

344

353

363

375

389

407.

432

473

543

662

838

1039

1) Al nunwcal values are presented at elevation %%ith peak pm~er

H-120
#B2OT l 1ndividufa mcweristics ofRefabricted Fuel Rods"

(Fresh'FQ W diaied Cladding) under IGR Tets'

Table 11-7.7. Mechanical Characteristics of Fuel Rod #B20T Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes

Clad outer Fuel hoop Fuel - clad gap Clad hoop Clad hoop Internal gas Time s temperature') strain1) width') j strain') stress1) pressure (S) (K (%) (mm) N%) (MPa) (MPa)

FRAP-T6 ISCAN FRAP-T6 SCANAIL FRAP-T6 SCAN FRAP-T6 ISCANAI FRAP-T6 ISCAN FRAP-T6 [SCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4A

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

296

313

318

324

331

339

347

356

367

380

395

417

450

507

606

760

948

1089

1183

1281

1303

1332

1402

1462

1508

1541

1591

1355

293

297

315

321

328

336

344

353

363

375

389

407

432

473

543

662

838

1039

0.00 1 0.00 1 0.08

0.01

0.04

0.05

0.06

0.07

0.08

0.10

0.11

0.13

0.15

0.19

0.24

0.34

0.52

0.82

1.21

1.58

1.82

1.94

2.00

2.04

2.06

2.05

2.04

2.01

1.99

1.90

1.35

0.01

0.03

0.04

0.05

0.05

0.06

0.07

0.08

0.10

0.12

0.14

0.19

0.27

0.42

0.67

1.02

1.35

0.08

0.08

0.08

0.08

0.08

0.08

0.08

0.08

0.08

0.08

0.08

0.07

0.07

0.07

0.06

0.05

0.04

0.03

0.03

1.78

2.45

2.45

2.45

2.45

2.45

2.45

2.46

2.48

0.08

0.08

0.08

0.08

0.08

0.08

0.08

0.08

0.08

0.08

0.08

0.08

0.08

0.08

0.07

0.07

0.06

0.05

0.01

0.01

0.02

0.02

0.03

0.03

0.04

0.04

0.05

0.06

0.07

0.08

0.09.

0.12

0.16

0.23

0.33

0.46

0.56

0.55

43.7

60.9

60.9

61.0

61.0

61.1

61.1

61.1

60.9

0.01

0.01

0.03

0.03

0.03

0.04

0.05

0.05

0.06

0.07

0.08

0.10

0.12

0.15

0.20

0.29

0.43

0.59

8.73

8.78

8.92

8.96

9.00

9.03

9.07

9.11

9.16

9.21

9.27

9.35

9.46

9.61

9.82

10.0

10.2

10.4

10.5

10.5

13.5

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

8.70

8.77

8.93

8.97

9.01

9.06

9.10

9.14

9.19

9.25

9.32

9.41

9.53

9.72

9.97

10.2

10.4

10.5

1.70

1.71

1.74

1.74

1.75

1.76

1.76

1.77

1.78

1.79

1.80

1.81

1.83

1.86

1.90

1.94

1.97

2.00

2.01

2.02

1.99

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

1.70

1.71

1.74

1.75

1.75

1.76

1.77

1.78

1.78

1.79

1.80

1.82

1.84

1.87

1.90

1.93

1.96

1.98

') All numerical values are presented at elevation %ith peak pomw

H-121

I .... !
#B2OT I 1ndividualiCharaWnsrcis of Refabricated Fuel Rods

(Fresh Fuel, Prei ladding) under IGR Tests

Table H-7.8. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #B20T

Axial interval Energy deposition at infinite time Fuel enthalpy

from-to at time (t=6.51 s)

(mm)-(mm) cal/g fuel J/g fuel per-unit cal/g fuel J/g fuel per-unit

23.0-37.3 173 725 1.00 125 525 1.00

37.3-51.6 167 699 0.97 121 507 0.97

51.6-65.9 163 684 0.94 118 496 0.94

65.9 - 80.2 160 672 0.93 116 487 0.93

80,2-94.5 160 669 0.92 116 485 0.92

94.5- 108.8 159 666 0.92 115 482 0.92

108.8 - 123.1 158 662 0.91 '114 480 0.91

123.1 - 137.4 158 663 0.92 115 481 0.92

137.4 - 151.7 157 659 0.91 114 478 0.91

151.7 - 166.0 155 651 0.90 112 471 0.90

180

160

• 140

-- 120

-

GJ 100

C 80

60

40

r- 20

0

I Ii I ................ o i. .. . ............. D o oi ! I I... bIii%. ...

-Energy deposition

- Fuel enthalpy

I 1

20 40 60 80 100 120 140 160 180

Axial coordinate (mm)

Fig. H-7.4. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6 Code

for Fuel Rod #B20T

H-122
#B2OT I ilndividliaf• -cterstics of Refabricated Fuel Rods

:(Fre'sh Fu .-radiated Cladding) under IGR Tests

1.2

mI

I.E

0

(I)

0

p4

1.0 -I I I--

0.8 -1-

0.6

A

5 -

L

~~1~

.11~ IV

0.4 -t0.2 -fI 2 3 4

Radial fuel coordinate (rmm)

160

140

120

100

' 80

- 60

, [-..4--- 1.0 s , I"41--2.0 s

I-o6. Os

l I II

40

20

0

1.0 1.5 2.0 2.5 3.0 3.5 4.0

Radial fuel coordinate (mm)

Fig. H-7.5. Radial Distributions of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #B20T

H-123
#B2OT ridividdal Characten:i•it'sofRefabricated Fuel Rods I(Fresh Fuelj, Prehir M~ Cladding) under IGR Tests

250

200

e- 150

o100

0

CII.-

50

0

2500

2000

1500

02.

E 1000

500

FRAP-T6

.... SCANAIR

PoNvr of fuel rod

Energy deposition --"--_

- -- Fuel enthalpy

0 Leakage of energy

Clad oxidation ene

0 A_

0 1 2 3 4 5 6 7 8 9 10

Time (s)

FRAP-T6

- - - SCANAIR

-- - Fuel centerline temperature

---- Clad outer temperature _"

-a- Heat transfer coefficient

200

160

Cu

120 0•-

80

40

0

0.15

Cu

E

40

0.06-9•

0

0

C.)

0.03-•

0.00

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. H-7.6. Energy and Temperature Characteristics Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes for Fuel Rod #B2OT

H-124

I "-:
#B2OT jilndividuaJ~ctenistics of Refabricated Fuel Rods

I •(Fresh Ft~~iiradiated Cladding) uider IGR Tests I

2.5

2.0

1.5

E

0.5

0.0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

20

16

G0

12 '

7

4)

0.6

0

3.0

2.4

E

1.8 1E

*0.

0.6

100

.-

0

0D

*0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. H-7.7. Cladding Mechanical Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #B20T

H-125
OB20T

2.5

2.0

T.1.5

1.0

0.5

0.0

Individual CharabinstcsofRefabricated Fuel Rods'

(Fresh Fuel' Preirra MCladding) under IGR Tests'

2500

2000

1500

1000

.... SCANIR -500

Fetoahoop strain

-- Fuel centerline temperature - Io

1 0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. H-7.8. Fuel Strain Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel Rod #B20T

H-126
#B2OT I idwar Vinodif cgittics ofRefabricated Fuel Rods I (Fresh Fufie~Tlradiated Cladding) under IGR Tests

Table 11-7.9. Some Results of PIE for Fuel Rod #B20T

Characteristic Value

1. Measured. parameters of cladding oxidation and cladding

deformation

1.1. Cladding thickness at elevation 80,30 mm correspondent to

different azimuthal angles (pm):

00 606 525

900 606 R

1800 677 663

2700 691 663

1.2. ZrO2 thickness at elevation 80, 30 mm correspondent to different

azimuthal angles (pum):

00 15 15

900 15 -

1800 15 15

2700 15 20

1.3. aZr(O) thickness at elevation 80, 30 mm correspondent to different

azimuthal angles (pm):

00 20 15

900 20 -

1800 15 15

2700 20 30

1.4. Clad hoop strain at elevation 80, 30 mm correspondent (%) 6.7 49.5

2. Measured parameters for FGR analysis

2.1. Internal gas composition (% by volume):

He

N2

02

Ar

CO2

Kr

Xe

2.2. Free gas volume (cm3)

2.3. Gas pressure inside fuel rod under normal condition (MPa)

2.4. Kr concentration in fuel (cm 3

/g fuel)

3. Measured parameters of cladding hydriding

3.1. Coefficient of hydride orientation (per-unit) 0.5

3.2. Hydrogen concentration (% by weight)

H-127
#B2OT .Individual Cha-ract ct offRefabricated Fuel Rods

(Fresh Fuel, Pre ir Cl1adding) under IGR Tests

Table 11-7.10. General Characteristic of Fuel Rod OB20T

Parameter Unit Value

Experiment FRAP-T6 SCANAIR

I Type of coolant -- air air air

2 Burnup MWd/kg U 0 0 0

3 Energy deposition in fuel rod cal/g fuel 161 161 161

4 Peak fuel enthalpy cal/g fuel - 125 -

5 Peak fuel temperature K 2143 -

6 Peak clad temperature K - 1593 -

7 Fuel rod failure Yes, No Yes Yes -

8 Type of failure:

- cladding rupture due to ballooning Yes, No Yes Yes -

- cladding rupture due to PCMI Yes, No No No -

- fragmentation of fuel rod Yes, No No --

9 Failure time s - 5.61 -

10 Fuel enthalpy at failure cal/g fuel - 120 -

11 Outer cladding temperature at failure K - 1282 -

12 Internal gas pressure at failure MPa - 1.99 -

13 ZrO2 thickness after test Pm 15-20 --

14 Residual clad hoop strain:

- peak value for ballooning area % 49.5 60.53 -

- other location 1) _ % 6.7 1.60

"Calculated values by FRAP-T6 and SCANAIR codes are average along height of fuel rod excluding ballooning region

H-128
H-129
#B21T I In6ivhdFiI ,hhr• ••"f R Idinatnd -u"l •'• I

,,~(Fresh Fuel, Pre _2f'~i ddiqg) undetl GR Tests

PositionW](00)

Positioni (900)

I

Fig. H-8.1. Appearance of Fuel Rod #B21T (photographs and X-ray photograph)

H-130
#B21T I FrediA4 , •- F&astics Iý _ R i ef u r Fuel GcRtesdodi

,(Fresh Fi:Thj~ri!-iiated Cladding) under JOR-Tests

r

p

I

L2~M

2I

Pnitinn 1

Fig. H-8.2. Cross-Section and Cladding Microstructure for Fuel Rod #B21T at 35 mm Elevation

H-131

I "• ! "
MI2T I :ldividual ChiaracterispsticJfRefabniac Fel os' I faFpidding under JOR-Tests "

Position 1

Fig. H-8.3. Cross-Section and Cladding Microstructure for Fuel Rod #B21T at 90 mm Elevation

H-132
#B21T I AFes lat ClIddin'i) rdidrIOR Tests I;ýýý,'-

Position I

Position2

Fig. H-8.4. Fuel Microstructure for Fuel Rod #B21T at 90 mm Elevation

H-133
#B21T I, ndividi~aI Ch'•rate~ ofdRefabricated FuelR6ds -

Table H-8.1. Time Dependent Energy Characteristics of Fuel Rod #B21T

Reactor Cumulative number of fissions Power of Energy deposition

Time energy in fuel rod (fiss) fuel rod in fuel rod

(s) deposi- U U Total cal/g fuel J/g fuel

tionti x10.1 4 x10-12 x10-14

1 (%)I

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

9.0

10.0

20.0

30.0

00

0.000

1.080

4.410

5.600

7.430

10.80

17.40

29.20

45.20

60.80

72.10

79.50

84.30

87.40

89.60

91.20

92.40

93.20

93.90

94.50

94.90

95.30

95.60

96.20

96.60

96.90

97.20

97.60

97.90

99.20

99.60

100.0

0.000

0.115.

0.469

0.596

0.791

1.150

1.850

3.110

4.810

6.470

7.670

8.460

8.970

9.310

9.540

9.710

9.830

9.930

10.00

10.10

10.10

10.10

10.20

10.20

10.30

10.30

10.30

10.40

10.40

10.60

10.60

10.70

0.000

0.065

0.265

0.336

0.446

0.647

1.050

1.750

2.710

3.650

4.330

4.770

5.060

5.250

5.380

5.480

5.550

5.600

5.640

5.680

5.700

5.720

5.740

5.780

5.800

5.820

5.840

5.860

5.880

5.960

5.980

6.030

0.000

0.116

0A72

0.599

0.796

1.150

1.860

3.130

4.840

6.510

7.720

8.510

9.020

9.360

9.600

9.760

9.890

9.980

10.10

10.10

10.20

10.20

10.20

10.30

10.30

10.40

10.40

10.40

10.50

10.60

10.70

10.70

0.000

0.651

1.510

2.140

3.570

6.920

13.50

21.70

25.20

20.50

13.80

8.910

5.870

4.000

2.830

2.080

1.580

1.240

0.993

0.815

0.664

0.562

0.480

0.339

0.255

0.202

0.168

0.143

0.113

0.029

0.015

0.000

0.000

1.310

5.360

6.800

9.030

13.10

21.10

35.40

54.80

73.70

87.50

96.50

102.0

106.0

109.0

111.0

113.0

114.0

115.0

115.0

116.0

116.0

117.0

118.0

118.0

119.0

119.0

120.0

120.0

122.0

123.0

126.0

0.000

5.480

22.40

28.50

37.80

54.80

88.30

148.0

229.0

309.0

366.0

404.0

427.0

444.0

456.0

465.0

473.0

477.0

481.0

481.0

486.0

486.0

490.0

494.0

494.0

498.0

498.0

502.0

502.0

511.0

515.0

527.0 ___________ .5. .5. £ 1 .5. 1

Maximum value of power is 25.2 kW (t = 3.20 s)

I) Current energy deposition per maximum energy deposition (at infinite time)

H-134

I
IB21T % Indivrd~a'imm~t Wcsi~f RefabriiciedFel Rods -ý

, (Nr 5Ated Claddinig) uinder IGR, Test3s z

Table H-8.2. Axial Energy Characteristics of Fuel Rod #B21T

Axial Cumulative number of fissions Maximum Energy deposition

coordinate at axial interval (fiss) power of at infinite time*

from lower u 235 U23 9 Total fuel rod cal/g fuel J/g fuel per-unit3 )

end of fuel X10 '

3 X10-11 x1O" (kW)

rod I t=3.20s

(mm)

5.0

i0.01)

15.0

20.0

25.0

30.0

35.0

40.0

45.0

50.0

55.0

60.0

65.0

70.0

75.0

80.0

85.0

90.0

95.0

100.0

105.0

110.0

115.0

120.0

125.0

130.0

135.0

140.0

145.0

150.02)

155.0

0.000

1.640

4.060

4.000

3.990

3.920

3.840

3.810

3.800

3.830

3.800

3.740

3.730

3.740

3.760

3.760

3.750

3.740

3.720

3.720

3.700

3.690

3.690

3.660

3.660

3.650

3.610

3.620

3.620

3.620

0.000

0.000

0.799

2.010

2.020

2.050

2.070

2.060

2.070

2.100

2.140

2.150

2.140

2.150

2.170

2.190

2.200

2.200

2.210

2.190

2.190

2.180

2.170

2.170

2.140

*2.130

2.120

2.090

2.080

2.070

2.050

0.000

0.000

1.650

4.080

4.020

4.010

3.940

3.860

3.830

3.820

3.850

3.830

3.760

3.750

3.760

3.780

3.780

3.780

3.760

3.750

3.750

3.720

3.720

3.710

3.690

3.680

3.670

3.630

3.640

3.640

3.640

0.000

0.000

0.387

0.959

0.943

0.941

0.926

0.906

0.898

0.897

0.904

0.898

0.883

0.881

0.883

0.888

0.887

0.887

0.884

0.880

0.880

0.873

0.872.

0.872

0.865

0.864

0.862

0.853

0.855

0.856

0.856

0.000

0.000

137.0

136.0

133.0

133.0

131.0

129.0

128.0

128.0

127.0

126.0

125.0

125.0

125.0

125.0

125.0

125.0

124.0

124.0

124.0

124.0

124.0

124.0

123.0

123.0

123.0

122.0

122.0

121.0

120.0

0.000

0.000

573.0

569.0

557.0

557.0

548.0

540.0

536.0

536.0

532.0

527.0

523.0

523.0

523.0

523.0

523.0

523.0

519.0

519.0

519.0

519.0

519.0

519.0

515.0

515.0

515.0

511.0

511.0

507.0

502.0

0.000

0.00

1.00

0.99

0.97

0.97

0.96

0.94

0.93

0.93

0.93

0.92

0.91

0.91

0.91

0.91

0.91

0.91

0.91

0.91

0.91

0.91

0.91

0.91

0.90

0.90

0.90

0.89

0.89

0.88

0.88

0.00

All numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate 1 2.5 mm.

1) Initial coordinate of fuel is 10.5 mum.

2) End coordinate of fuel is 152.5 mm.

3) Current value per maximum value.

H-135
#B21T Individual',hiairaen4'ilcsofRefabricated Fuel Rods -

:(Fresh Fuel,PretiqaM Cladding) under IGR Tests,.

Table 11-8.3. Radial Energy Characteristics of Fuel Rod NB21T

Coordinates of fuel zones (mm)

Characteristics* I zone 2 zone 3 zone 4 zone

1.10 -2.12 2.12 -2.79 2.79 -3.32 3.32 -3.79

Number of fissions x !0"14 (fiss) 2.580 2.620 2.690 2.790

Power of fuel rod') (kW) 6.060 6.160 6.330 6.550

U235 Energy deposition 2

) (callg fuel) 121.0 123.0 126.0 131.0

Energy deposition 2) (J/g fuel) 507.0 515.0 527.0 548.0

Energy deposition3) (per-unit) 0.924 0.939 0.962 1.000

Number of fissions x 10"12 (fiss) 1.520 1.510 1.500 1.510

Power of fuel rodt) (kW) 0.035 0.035 0.035 0.035

U238 Energy deposition 2

) (cal/g fuel) 0.701 0.696 0.694 0.696

Energy deposition 2) (J/g fuel) 2.930 2.910 2.910 2.910

Energy deposition3) (per-unit) 1.000 0.993 0.990 0.993

Number of fissions X10"14 (fiss) 2.600 2.640 2.710 2.800

Power of fuel rod') (kW) 6.100 6.200 6.360 6.580

Total Energy deposition2) (cal'g fuel) 122.0 124.0 127.0 131.0

Energy deposition2) (J/g fuel) 511.0 519.0 532.0 548.0

1 Energy deposition3) (per-unit) 0.931 0.947 0.969 1.000

at time of3.20 s. 2) at infinite time, 3) Current value per maximum value

All numerical values of characteristics were calculated for length of fuel stack

H-136
#B21T individuAfiiSibteristics of Refabricated Fuel Rods I(Fresh Fe-'&Ire diated Cladding) under IGR Tests,

Table 11-8.4. Fuel Enthalpy Vs. Time Calculated by FRAP-T6 Code for Fuel Rod #B21T

Time Enthalpy at fuel radius Fuel enthalpy Energy deposition

Time __ (cal/ fuel) __ Fuel thalpy _ ) in fuel rod

(S) 1.10rmI 2.22mm 2.89mm 3.79mm cal/gifuel J/Ig calfg fuel J/g fuel

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

1.19

4.77

6.08

8.16

12.1

20.1

34.6

54.5

74.0

88.3

97.3

103

106

107

107

106

105

104

103

102

101

100

98.4

96.9

95.7

94.6

91.4

71.8

0.00

1.18

4.70

5.99

8.06

12.0

20.0

34.4

54.1

73.1

86A

94.3

983

100

101

100

99.7

99.0

98.4

97.9

97.5

97.1

96.7

95.7

94.8

93.9

93.1

90.4

71.4

0.00

1.15

4.56

5.82

7.84

11.7

19.5

33.5

52.2

69.5

80.5

86.3

89.0

90.1

90.2

90.1

90.1

90.5

91.2

91.8

92.1

92.3

92.4

92.3

91.9

91.4

90.9

88.8

70.7

0.00

1.06

4.19

5.33

7.15

10.5

17.1

28.0

40.9

51.6

58.8

64.1

67.5

69.5

71.3

74.0

782

81.9

83.7

84.9

85.7

86.2

86.6

87.2

87.4

87.4

87.2

86.0

69.5

0.00

1.15

4.57

5.82

7.83

11.6

19.4

33.1

51.2

.68.1

79.4

86.0

89.7

91.4

92.1

92.4

92.9

93.5

93.8

94.0

94.0

93.9

93.8

932

92.6

92.0

91.4

0.00

4.81

19.1

24.4

32.8

48.8

81.1

139

215

285

333

361

376

383

386

387

389

392

393

394

394

393

393

391

388

386

383

373

297

0.00

1.31

5.36

6.81

9.04

13.1

21.2

35.5

54.9

73.8

87.6

96.6

103

106

109

111

113

114

115

115

116

116

117

118

118

119.

119

120

123

0.00

5.51

22.5

28.5

37.9

54.9

88.7

149

230

309

367

405

430

446

457

466

472

477

480

483

486

488

490

493

496

498

499

504

517

89.1

70.9

Radial enthalpy distribution and fuel enthalpy are presented at elevation 17.6 mm

Maximum value of fuel enthalpy is 94.0 cad/g fuel (t-5.51 s)

1 All numerical values are presented at elevation %ith peak poDr

H-137

I --,
#B21T .Individtai Claramc~ rillef Refabricated Fuel Rods F~l.PCladding)udO / M IT(Fresh Fuel, PreiEýPW addng under IGR Tets~

Table H-8.5. Energy Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel

Rod #B21T

T Energy Linear Clad-to-coolant heat

T e 1) Fuel enthalpy) Leakage of energy' ) rfer Coefficient1) () deposition") PowCr) (eal/g fuel) (ca~g fuel) trnfr'Mit

(s) (ca/g fuel) (kW/m) (kW/m2

K)

FRAP-T6I SCANAIR FRAP-T6 SCANAIR FRAP-T6 SCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5A

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

1.40

5.70

7.23

9.60

13.9

22.5

37.7

58.3

78.4

93.1

103

109

113

116

118

120

121

122

123

123

124

124

125

126

126

127

128

131

0.00

4.84

11.2

15.9

26.5

51.5

100

161

187

152

103

66.3

43.7

29.7

21.0

15.5

11.7

9.22

7.38

6.06

4.94

4.18

3.57

2.52

1.90

1.50

1.25

0.84

0.11

0.00 0.00

1.15

4.57

5.82

7.83

11.6

19A

33.1

51.2

68.1

79.4

86.0

89.7

91.4

92.1

92.4

92.9

93.5

93.8

94.0

94.0

93.9

93.8

93.2

92.6

92.0

91.4

89.1

70.9

1.26

4.89

6.19

8.24

12.1

19.7

33.1

50.8

67.1

78.1

84.5

88.1

0.00

0.00

0.00

0.00

0.00

0.01

0.01

0.02

0.03

0.05

0.10

0.19

0.31

0.45

0.61

0.81

1.03

1.28

1.54

1.81

2.08

2.37

2.66

3.43

423

5.06

5.91

9.39

37.1

0.00

0.00

0.00

0.00

0.01

0.01

0.01

0.02

0.03

0.07

0.13

0.23

0.37

0.00

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.02

0.02

0.03

0.04

0.05

0.06

0.06

0.07

0.07

0.07

0.07

0.08

0.08

0.08

0.08

0.08

0.08

0.09

0.09

0.09

0.06

0.00

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.02

0.03

0.04

0.05

0.06

1) All nunx-rical vauecs arc prescnted at elevation %ith peak powcr

H-138
#B21T rI ds of Refabricated Fuel Rods

:(Fresh Fu *ir~adiated Cladding) under IGR Tests

Table 11-8.6. Temperature Variation, Fission Gas Release and ZrO2 Thickness Vs. Time for Fuel

Rod #B21T Calculated by FRAP-T6 and SCANAIR Codes

Fuel centerline Fuel surface Clad outer Time temperature') temperature') temperature')

(S) (K) -_ (K) (K)

FRAP-T6 SCANAIR FRAP-T6 SCANAIR IRAP-T6 SCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

.293

314

374

395

427

487

604

806

1073

1328

1509

1623

1688

1723

1738

1740

1734

1722

1708

1694

1680

1668

1658

1635

1617

1602

1589

1549

1300

293

313

372

392

424

480

588

772

1011

1237

1397

1499

1561

293

312

364

383

411

463

561

716

892

1035

1131

1199

1243

1269

1293

1327

1382

1429

1452

1467

1477

1484

1489

1496

1498

1498

1496

1481

1270

293

313

367

386

416

470

574

738

928

'1081

1180

1246

1285

293

299

328

338

351

371

406

474

588

738

887

1010

1082

1132

1177

1233

1266

1276

1286

1297

1308

1319

1329

1349

1365

1376

1383

1387

1211

293

300

331

342

357

380

423

503

631

789

940

1062

1134

H-139
#B21T SIndividual'ChiaikigcofRefabricated Fuel Rods*

(Fresh Fuel,'Preirfia MClading) under IOR Tests'

Table H-8.7. Mechanical Characteristics of Fuel Rod #B21T Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes

Clad outer Fuel hoop Fuel - clad gap Clad hoop Clad hoop Internal gas Time temperature') strain"s width') strain" stressi) pressure ___(K) (%) (mm) (%0 (MPa) (MPa)

RP.-T61SCANA4 FR".T6RSCANA -FRANT61S C E FRAN.T6 FRAP.T6SCANA FRAP-T6 SCANAR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

*5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

299

328

338

351

371

406

474

588

738

887

1010

1082

1132

1177

1233

1266

1276

1286

1297

1308

1319

1329

1349

1365

1376

1383

1387

1211

293

300

331

342

357

380

423

503

631

789

940

1062

1134

0.00

0.01

.0.07

0.09

0.12

0.18

0.30

0.50

0.78

1.07

1.27

1.40

1.47

1.50

1.51

1.52

1.52

1.52

1.51

1.51

1.50

1.49

1.49

1.47

1.45

1.44

1.43

1.38

1.08

0.00

0.01

0.05

0.07

0.09

0.14

0.23

0.40

0.64

0.88

1.05

1.16

1.22

0.08

0.07

0.07

0.07

0.07

0.07

0.07

0.06

0.05

0.05

0.04

0.04

0.04

0.04

0.04

0.06

0.21

2.05

2.05

2.05

2.05

2.05

2.05

2.05

2.05

2.05

2.05

2.05

2.06

0.08

0.08

0.07

0.07

0.07

0.07

0.07

0.07

0.06

0.06

0.05

0.05

0.05

0.01

0.01

0.03

0.04

0.05

0.06

0.09

0.13

0.21

0.32

0.42

0.50

0.55

0.57

0.61

0.88

4.26

51.2

51.2

51.2

51.2

51.2

51.2

51.2

51.2

51.3

51.3

51.3

51.2

0.01

0.01

0.04

0.05

0.06

0.08

0.11

0.17

0.27

0.39

0.51

0.60

0.56

8.72

8.81

9.04

9.11

9.20

9.35

9.57

9.84

10.1

10.2

10.3

10.4

10.4

10.4

10.5

10.6

11.2

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

8.69

8.80

9.04

9.12

9.22

9.38

9.64

9.95

10.2

10.3

10.3

10.3

10.1

1.70

1.72

1.76

1.77

1.79

1.82

1.86

1.90

1.95

1.98

1.99

2.00

2.01

2.01

2.01

2.02

2.00

0.10

0.10

,0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

1.70

1.72

1.76

1.77

1.79

1.81

1.85

1.89

1.93

1.95

1.96

1.96

1.97

AlD numerical values are prcscntcd at elevation with peak powcr

H-140

I +--
#B21T I rndividua1: ti stics of Refabricated Fuel Rods

I.(F h Fueiiradiated Cladding) under IGR Tests.

Table H-8.8. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod IB21T

Axial interval Energy deposition at infinite time Fuel enthalpy

from-to at time (t5.51 s)

(mm)-(mm) caVg fuel Jig fuel per-unit caVg fuel J/g fuel per-unit

10.5-24.7 134 561 1.00 94.0 394 1.00

24.7-38.9 130 544 0.97 91.2 382 0.97

38.9 - 53.1 127 534 0.95 89.5 375 0.95

53.1 - 67.3 126 526 0.94 88.2 369 0.94

67.3 - 81.5 126 526 0.94 88.2 369 0.94

81.5 -95.7 124 520 0.93 87.2 365 0.93

95.7- 109.9 124 520 0.93 87.2 365 0.93

109.9 - 124.1 124 520 0.93 87.2 365 0.93

124.1 - 138.3 123 516 0.92 86.5 362 0.92

138.3 - 152.5 121 509 0.91 85.3 357 0.91

140

• 120

Cu !Uo

80

IE60

40

• 20

......... .. .. ..... ....

Energy deposition

.... Fuel enthalpy

0 I

0 30 60 90

Axial coordinate (mm)

120 150 180

Fig. H-8.5. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6 Code

for Fuel Rod #B21T

H-141
#B21T

SindlividýiA'Chaiw'an•kof Refabricated Fuel Rods ;." •J•'

,(Fresh Fuel, Preif m Cladding) under IGR Tests'

1.2

I)

0

1.0 .4 + ___________

0.8 --

0.6 -I- II Ivý

0.4 -jI

0.2-I- ~1~

1. 2 3 4

Radial fuel coordinate (mm)

* 120

100

-- w- 1.0

-. 0-2. 0

-V-- 3.0 s

I0-.

80

60

40

-]--

20

A

4 ~ - ~.a

0 'I. I I

1.0 1.5 2.0 2.5 3.0 3.5 4.0

Radial fuel coordinate (mm)

Fig. H-8.6. Radial Distributions of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #B2T

H-142
#B21T I 1ndividtual.- r~idstics of Refabricated Fuel Rods"

I (Fresh Fu~f~~~adiated Clidding) tinder IGR Tests -

200

160

-120

80

2000

1600

1200

r 800

400

0

150

120

90 .

60"

c- i

U

30

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

0.10

"E

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. H-8.7. Energy and Temperature Characteristics Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes for Fuel Rod #B21T

H-143
MIB2T I Individuil ChiarAcNi of Refabricated Fuel Rods,,

'(Fresh Fuel, Prc4•Cladding) under IGR Tests

2.5

2.0

2' 1.5

4)

E

0.5

0.0

60

50

40

,30

U 20

10

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

15

12

S

9 V)

0

0

3

0

3.0

2.5

2.0 E

1.5 •

1.0 Y

0.5

0.0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. H-8.8. Cladding Mechanical Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #B21T,

H-144

I --,
#B21T I Jndividualara~edstics of Refabricated Fuel Rods

(Frs FiM etrradiated Cladding) under IGR Tests - t .,

2.0

1.6

" 1.2

0

0.8

0.4

0.0

2000

1600

1200

E

0.

800 U

U

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. H-8.9. Fuel Strain Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel Rod NB21T

H-145
Individual 'Chaiadcfs~s'of Rifabricated Fuel Rods M I 1T (Fhel Fuel, Pieia ladding) udiIRT

Table 11-8.9. Some Results of PIE for Fuel Rod #B21T

Characteristic Value

1. Measured parameters of cladding oxidation and cladding

deformation

1.1. Cladding thickness at elevation 35, 90 mm correspondent to

different azimuthal angles (pim):

00 705 670

900 649 649

1800 175 649

2700 649 677

1.2. ZrO2 thickness at elevation 35, 90 mm correspondent to different

azimuthal angles (pm):

00 20 40

900 25 50

1800 20 40

2700 20 40

1.3. ctZr(O) thickness at elevation 35, 90 mm correspondent to different

azimuthal angles (pm):

00 30 50

900 30 50

1800 30 35

2700 40 40

1.4. Clad hoop strain at elevation 35, 90 mm correspondent (%) 16.9 7.2

2. Measured parameters for FGR analysis

2.1. Internal gas composition (% by volume):

He

N2

02

Ar

CO2

Kr

Xe

2.2. Free gas volume (cm3)

2.3. Gas pressure inside fuel rod under normal condition (MPa)

2.4. Kr concentration in fuel (cm 3

/e fuel)

3. ' Measured parameters of cladding hydriding

3.1. Coefficient of hydride orientation (per-unit)

3.2. Hydrogen concentration (% by weight)

H-146

I -_
#B21T indivndualt hk cteristics of Refabricated Fuel Rods - I(Fresh .e irradiated Cladding) under IGR Tests

Table 11-8.10. General Characteristic of Fuel Rod NB21T

Parameter Unit Value

Experiment FRAP-T6 SCANAIR

1 Type of coolant air air air

2 Burnup MWd/kg U 0 0 0

3 Energy deposition in fuel rod cal/g fuel 126 126 126

4 Peak fuel enthalpy cal/g fuel - 94

5 Peak fuel temperature K 1740

6 Peak clad temperature K 1389

7 Fuel rod failure Yes, No Yes Yes

8 Type of failure:

- cladding rupture due to ballooning Yes, No Yes Yes -

- cladding rupture due to PCMI Yes, No No No -

- fragmentation of fuel rod Yes, No No --

9 Failure time s - 4.91 -

10 Fuel enthalpy at failure cal/g fuel - 93 -

11 Outer cladding temperature at failure K - 1272 -

12 Internal gas pressure at failure MPa - 1.98 -

13 ZrO2 thickness after test Pm 20-50 --

14 Residual clad hoop strain:

- peak value for ballooning area % 50.86 -

- other location_ % _ 7.2 1.69 -

"

1

Calculated values by FRAP-T6 and SCANAIR codes are average along height of fuel rod excluding ballooning region

H-147

i --

H-149
#B22T -ýFrc'sh Fuel.; P widaated qadding)'u'ndei IOR Tests

Fig. H-9.1. Appearance of Fuel Rod #B22T (photographs and X-ray photograph)

H-150
#B22T I ndciv icf '"stics of Refabriicat FuIe d Rods"

(F[ reshIu iadiated Cladding) under IOR Tests

Position 1

Position 2

Fig. H-9.2. Cross-Section and Cladding Microstructure for Fuel Rod #B22T at 35 mm Elevation

H-151

I -
I#B22T .(Fri Fuel;. Pf lgM dding) under IGR Teos-s .

11

Pne~itinn 1

Fig. H-9.3. Cross-Section and Cladding Microstructure for Fuel Rod 8B22T at 90 mm Elevation

H-152

I _,__
#B22T Indivifdh(Tia Tahties of Rcfabdringt&mdcr R-tCI Rd';d• I (Frc Mwb!M*Igf~rrdaed Cladding) under JOR Teitshti,

Position 1

an

Position2

Fig. H-9.4. Fuel Microstructure for Fuel Rod #B22T at 90 mm Elevation

H-153
#B22T (Fresh ýidn gunder-GRTss -n '-

Table H-9.1. Time Dependent Energy Characteristics of Fuel Rod #B22T

Reactor Cumulative number of fissions Power of Energy deposition

Time energy in fuel rod (fiss) fuel rod in fuel rod

(s) deposi- u I 3 Total (kW) cal/g fuel J/g fuel

tionI xl0"14 x10"12 X10"14

N%

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

9.0

10.0

20.0

30.0

00

0.000

0.910

3.880

4.990

6.580

9.150

13.80

22.60

37.10

52.70

65.80

75.60

82A0

87.00

90.10

92.10

93.40

94.30

94.90

95.30

95.60

95.90

96.10

96.60

96.90

97.20

97.40

97.70

98.00

99.20

99.60

100.0

0.000

0.078

0.334

0.430

0.568

0.788

1.190

1.950

3.200

4.540

5.670

6.520

7.100

7.500

7.760

7.940

8.050

8.130

8.180

8.210

8.240

8.260

8.280

8.320

8.350

8.370

8.390

8.420

8.450

8.550

8.580

8.650

0.000

0.044

0.188

0.243

0.320

0.445

0.670

1.100

1.800

2.560

3.200

3.680

4.010

4.230

4.380

4.480

4.540

4.580

4.610

4.630

4.650

4.660

4.670

4.700

4.710

4.720

4.730

4.750

4.770

4.820

4.840

4.880

0.000

0.079

0.336

0.432

0.571

0.793

1.190

1.960

3.210

4.570

5.700

6.550

7.140

7.540

7.810

7.980

8.100

8.170

8.220

8.260

8.290

8.310

8.330

8.370

8.400

8.420

8.440

8.470

8.490

8.600

8.630

8.700

0.000

0.443

1.160

1.590

2.390

4.050

7.640

14.30

19.70

17.80

14.00

10.00

6.870

4.600

3.050

2.030

1.370

0.933

0.649

0.485

0.413

0.355

0.308

0.226

0.176

0.144

0.123

0.105

0.085

0.022

0.012

0.000

0.000

0.897

3.830

4.930

6.500

9.030

13.60

22.30

36.60

52.00

65.00

74.60

81.40

86.00

89.10

91.10

92.50

93.40

94.00.

94.50

94.80

95.20

95.40

96.00

96A0

96.70

97.00

97.40

97.80

99.50

100.0

102.0

0.000

3.750

16.00

20.60

27.20

37.80

56.90

93.30

153.0

218.0

272.0

312.0

341.0

360.0

373.0

381.0

387.0

391.0

393.0

396.0

397.0

399.0

399.0

402.0

404.0

405.0

406.0

408.0

409.0

417.0

419.0

427.0

Maximum value orpower is 19.7 kW (t - 3.20 s)

1) Current energy deposition per maximum energy deposition (at infinite time)

H-154
#B22T I ydo l id.ten of Refab'rclatddiýFelRod"R s -ý.' ,-:.,-

(Frh 1; =~~ac Cladding) widerIGR Tests,"

Table H-9.2. Axial Energy Characteristics of Fuel Rod #B22T

Axial Cumulative number of fissions Maximum Energy deposition

coordinate at axial interval (fiss) power of at infinite time*

from lower u23 u23 Total fuel rod calg fuel J/g fuel per-unit3 )

end of fuel x(103 X10" xi1(W)

rod t=-3.20s

(mm)

5.0

10.00)

15.0

20.0

25.0

30.0

35.0

40.0

45.0

50.0

55.0

60.0

65.0

70.0

75.0

80.0

85.0

90.0

95.0

100.0

105.0

110.0

115.0

120.0

125.0

130.0

135.0

140.0

145.0

150.02)

155.0

0.000

1.350

3.320

3.270

3.190

3.150

3.140

3.110

3.090

3.090

3.070

3.040

3.030

3.030

3.000

3.000

2.990

2.990

3.010

3.010

3.000

2.980

2.980

3.000

2.990

2.970

2.950

2.940

2.930

2.910

0.000

0.000

0.653

1.640

1.650

1.650

1.660

1.680

1.690

1.700

1.730

1.740

1.740

1.750

1.750

1.750

1.750

1.760

1.760

1.770

1.770

1.770

1.760

1.750

1.750

1.740

1.720

1.710

1.690

1.670

1.650

0.000

0.000

1.350

3.340

3.290

3.200

3.170

3.160

3.130

3.110

3.110

3.090

3.060

3.050

3.040

3.020

3.010

3.010

3.010

3.020

3.020

3.020

3.000

3.000

3.010

3.010

2.980

2.970

2.960

2.940

2.930

0.000

0.000

0.306

0.755

0.745

0.726

0.717

0.716

0.709

0.704

0.704

0.699

0.692

0.691

0.689

0.683

0.682

0.682

0.681

0.685

0.685

0.684

0.680

0.679

0.683

0.681

0.676

0.673

0.670

0.667

0.662

0.000

0.000

112.0

111.0

109.0

107.0

106.0

105.0

104.0

103.0

103.0

103.0

102.0

101.0

102.0

101.0

101.0

101.0

101.0

101.0

101.0

101.0

100.0

100.0

100.0

100.0

99.80

99.70

99.30

98.70

98.10

0.000

0.000

469.0

465.0

456.0

448.0

444.0

440.0

435.0

431.0

431.0

431.0

427.0

423.0

427.0

423.0

423.0

423.0

423.0

423.0

423.0

423.0

419.0

419.0

419.0

419.0

418.0

417.0

416.0

413.0

411.0

0.000

0.00

1.00

0.99

0.97

0.96

0.95

0.94

0.93

0.92

0.92

0.92

0.91

0.90

0.91

0.90

0.90

0.90

0.90

0.90

0.90

0.90

0.89

0.89

0.89

0.89

0.89

0.89

0.89

0.88

0.88

0.00

* All numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate + 2.5 mm.

I) Initial coordinate of fuel is 10.5 mm.

2) End coordinate of fuel is 152.5 nun.

3) Current value per maximum value.

H-155

I -
#B22T Individual d teraderrS~fRefabricated Fuel Rods 7.

I FehFel, Prei iýtqCladding) under IGR Tests

Table H-9.3. Radial Energy Characteristics of Fuel Rod #B22T

Coordinates of fuel zones (mm)

Characteristics* I zone 2 zone 3 zone 4 zone

1.10 -2.12 2.12 -2.79 2.79 -3.32 3.32-3.79

Number of fissions xl 0" 4 (fiss) 2.090 2.120 2.180 2.260

Power of fuel rod') (kW) 4.730 4.810 4.940 5.110

U 235 Energy deposition2) (cal/g fuel) 98.30 99.80 103.0 106.0

Energy deposition 2

) (J/g fuel) 411.0 418.0 431.0 444.0

Energy deposition3) (per-unit) 0.927 0.942 0.972 1.000

Number of fissions x 10-12 (fiss) 1.230 1.220 1.220 1.220

Power of fuel rod') (kW) 0.027 0.027 0.027 0.027

U2 8 Energy deposition2) (cal/g fuel) 0.569 0.565 0.564 0.565

Energy deposition2) (J/g fuel) 2.380 2.370 2.360 2.370

Energy deposition3) (per-unit) 1.000 0.993 0.991 0.993

Number of fissions x10-'4 (fiss) 2.100 2.140 2.190 2.270

Power of fuel rod') (kW) 4.760 4.840 4.970 5.140

Total Energy deposition2) (cal/g fuel) 98.90 100.0 103.0 107.0

Energy deposition 2) (J/g fuel) 414.0 419.0 431.0 448.0

Energy deposition3) (per-unit) 0.924 0.935 0.963 1.000

at time or3.20 s, 2) at infinite time, 3) Current value per maximum value

All numerical values orcharacteristics were calculated for length of fuel stack

H-156

{ ..... • ._
#B22T SIlndividual•' d -ic stics of Refabricated Fuel Rods ., I

I FrsFuiiadac Cladding) under IGR Tests.

Table 11-9.4. Fuel Enthalpy Vs. Time Calculated by FRAP-T6 Code for Fuel Rod #B22T

Time Enthalpy at fuel radius Fuel enthalpy Energy deposition

Time_ (cal/g fuel) _ Fuel nthalpy _ ) in fuel rod

(S) 1.10mm I 2.22mm 2.89mm 3.79mm caL/gfifel J/gfuet cal/g fuel Jilgfuel

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0-

10.0

30.0

0.00

0.83

3A5

4.46

5.94

8.38

12.9

21.9

36.6

52.8

66.3

76.2

82.8

86.7

88.7

89.3

89.1

88.3

87.3

86.1

85.0

83.9

82.9

80.9

79.6

.78.6

78.0

76.2

63.0

0.00

0.82

3.40

4.40

5.87

8.29

12.8

21.7

36A

52.2

65.1

74.2

79.8

82.8

84.2

84.5

84.2

83.5

82.7

81.9

81.1

80.4

79.9

78.8

78.1

77.5

77.1

75.6

62.7

0.00

0.80

3.31

4.28

5.70

8.07

12.5

21.2

35.4

50.1

61.4

68.8

73.2

75.4

76.5

76.9

76.9

76.7

76.5

76.3

76.2

76.1

76.1

76.1

76.2

76.1

75.9

74.7

62.3

0.00

0.74

3.05

3.93

5.23

7.34

11.2

18.4

29.2

39.2

46.8

52.4

56.6

59.9

62.5

64.3

65.7

66.9

68.1

69.1

70.2

71.0

71.6

73.0

73.8

74.0

73.9

73.0

61.5

0.00

0.80

-3.31

4.28

5.70

8.06

12.4

21.0

34.8

49.2

60.6

68.4

73.4

76.3

77.9

78.6

78.7

78.6

78.3

78.0

77.8

77.6

77.4

77.0

76.8

76.5

76.2

74.9

62.4

0.00

3.36

13.9

17.9

23.9

33.8

52.2

87.9

146

206

254

287

307

320

326

329

330

329

328

327

326

325

324

323

322

321

319

314

261

0.00

0.90

3.82

4.92

6.50

9.03

13.6

22.3

36.6

52.0

64.9

74.6

81.4

86.0

89.1

91.1

92.5

93.4

94.0

94.5

94.8

95.1

95.4

95.9

96.3

96.7

96.9

97.8

100

0.00

3.76

16.0

20.6

27.2

37.8

57.0

93.4

153

218

272

313

341

360

373

382

387

391

394

396

397

399

400

402

404

405

406

410

419 .5. .5. 5 1. L S

Radial enthalpy distribution and fuel enthalpy are presented at elevation 17.6 mnm

Max'imum value of fuel enthalpy is 78.7 cat'g fuel (t-4.78 s)

I) All numrical values are presented at elevation %hith peak povxT

H-157
#B22T F

individual Cih'aactWe cobfRefabricated Fuel Rods

(Fresh Fuel. Preir"iMa-tdCadding) under IGR Tests

Table H-9.5. Energy Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel

Rod #B22T

Time Tie Energy neg Linear Lner Fuel enhapy Leakage of energy') Clad-to-coolant heat transfer coefficient'0

() depositionO Pow~rr (eal/g fuel) (cal/g fuel) tase ofiin'

(s) (eal/g fuel) (kW/m) (kW/m2 K)

F1AP-T6_S___AI__ FRAP-T6 SCANAIR FRAP-T6 SCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

-10.0

30.0

0.00

0.96

4.11

5.29

6.98

9.70

14.6

24.0

39.3

55.9

69.8

80.2

87.5

92.4

95.7

97.9

99.3

100

101

101

102

102

102

103

103

104

104

105

108

0.00

3.34

8.75

12.0

18.0

30.5

57.6

108

149

134

106

75.4

51.8

34.7

23.0

15.3

10.3

7.04

4.90

3.66

3.12

2.68

2.32

1.70

1.33

1.09

0.93

0.64

0.09

0.00

0.80

3.31

4.28

5.70

8.06

12.4

21.0

34.8

49.2

60.6

68.4

73.4

76.3

77.9

78.6

78.7

78.6

78.3

78.0

77.8

77.6

77.4

77.0

76.8

76.5

76.2

74.9

62.4

0.00

0.88

3.60

4.62

6.10

8.51

12.9

21.3

35.0

49.0

60.1

67.8

72.8

75.8

77.5

78.3

78.5

0.00

0.00

0.00

0.00

0.00

0.00

0.01

0.01

0.02

0.03

0.05

0.10

0.16

0.25

0.37

0.51

0.66

0.83

1.01

121

1A2

1.63

1.86

2.43

3.03

3.63

4.24

6.64

26.3

0.00

0.00

0.00

0.00

0.00

0.01

0.01

0.01

0.02

0.04

0.07

0.12

0.20

0.30

0.43

0.58

0.75

0.00

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.02

0.02

0.03

0.04

0.04

0.05

0.05

0.06

0.06

0.06

0.07

0.07

0.07

0.07

0.07

0.07

0.07

0.07

0.07

0.05

0.00

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.02

0.03

0.03

0.04

0.05

0.05

0.06

0.06

~ J. A. A. - I - -

1) All nturcrical values are presented at elevation Wdith peak pov-r

H-158

1,-
#B22T I indivIduaV.Mterisics of Refabricated Fuel Rods I (Fresh F-u-u•'rt~ diated Cladding) under IGR Tests' ,

Table H-9.6. Temperature Variation, Fission Gas Release and ZrO2 Thickness Vs. Time for Fuel

Rod #B22T Calculated by FRAP-T6 and SCANAIR Codes

Fuel centerline Fuel surface Clad outer

(s) temperature') temperature') temperature])

(___(K) (K) (K)

FRAP-T6 SCANAIR FRAP-T6 SCANAIR FRAP.T6 SCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

308

352

369

392

431

499

629

834

1051

1228

1356

1440

1489

1514

1522

1520

1510

1497

1482

1468

1454

1442

1417

1399

1387

1379

1356

1185

293

307

351

368

391

427

492

612

798

993

1152

1267

1345

1394

1423

1437

1442

293

306

346

360

381

414

473

579

732

869

971

1046

1102

1145

1178

1202

1220

1236

1251

1265

1278

1289

1297

1315

1325

1327

1326

1315

1165

293

307

348

363

385

420

483

595

758

904

1010

1085

1140

1180

1208

1223

1232

293

297

318

325

335

349

371

411

484

595

718

834

931

1009

1069

1111

1143

1172

1198

1218

1232

1242

1249

1257

1258

1258

1258

1254

1126

293

298

320

329

340

356

382

430

516

636

764

881

977

1053

1104

1135

1157

H-159
#B22T Indivduidl Charactsts' fRefabricatýd Fuel Rods

'(resh Fuel.'PrircrA'4' -Cladding) under IGR Tests

Table H-9.7. Mechanical Characteristics of Fuel Rod #B22T Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes

Clad outer Fuel hoop Fuel - clad gap Clad hoop Clad hoop Internal gas

Ti(s) temperature') strain"N width') strain1) stress') pressure S (K) (%) (mm) (%) (MPa) (MPa)

FRAPT-6 ISCAN FRAP-T6 SCAN FRAP-T6ISAI FWP-T6 SCAN F P.T61SCAN FRAP-T6 SCANAM

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

.5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

297

318

325

335

349

371

411

484

595

718

834

931

1009

1069

1111

1143

1172

1198

1218

1232

1242

1249

1257

1258

1258

1258

1254

1126

293

298

320

329

340

356

382

430

516

636

764

881

977

1053

1104

1135

1157

0.00

0.01

0.05

0.07

0.09

0.13

0.20

0.32

0.53

0.75

0.94

1.08

1.17

1.23

1.25

1.26

1.26

1.26

1.25

1.24

1.23

1.22

1.21

1.19

1.18

1.17

1.17

1.14

0.94

0.00

0.01

0.04

0.05

0.07

0.10

0.15

0.25

0.42

0.61

0.78

0.89

0.97

1.02

1.04

1.06

1.06

0.08

0.08

0.07

0.07

0.07

0.07

0.07

0.07

0.06

0.05

0.05

0.05

0.05

0.05

0.05

0.05

0.05

0.05

0.06

0.07

0.09

0.11

0.14

0.29

2.35

2.35

2.35

2.35

2.36

0.08

0.08

0.07

0.07

0.07

0.07

0.07

0.07

0.07

0.06

0.06

0.06

0.06

0.06

0.06

0.06

0.06

0.01

0.01

0.02

0.03

0.04

0.05

0.06

0.09

0.14

0.22

0.30

0.38

0.45

0.50

0.54

0.56

0.57

0.61

0.68

0.91

1.40

1.82

2.48

6.08

59.2

59.2

59.2

59.2

59.4

0.01

0.01

0.03

0.04

0.04

0.06

0.08

0.11

0.18

0.27

0.37

0.46

0.54

0.59

0.60

0.56

.0.52

8.72

8.78

8.94

8.99

9.06

9.16

9.30

9.51

9.73

9.89

9.99

10.0

10.1

10.1

10.1

10.1

10.1

10.1

10.2

10.2

10.3

10.4

10.6

11.2

0.00

0.00

0.00

0.00

0.00

8.69

8.77

8.96

9.03

9.11

9.23

9.42

9.68

9.98

10.2

10.2

10.2

10.2

10.2

10.0

10.1

10.1

1.70

1.71

1.74

1.75

1.76

1.78

1.81

1.84

1.88

1.91

1.93

1.94

1.95

1.95

1.95

1.95

1.95

1.95

1.95

1.95

1.95

1.95

1.95

1.94

0.10

0 .10

0.10

0.10

0.10

1.70

1.71

1.75

1.76

1.77

1.79

1.82

1.86

1.90

1.92

1.94

1.95

1.95

1.96

1.96

1.96

1.96

N

) All nmncrical values are presented at elevation with peak poutr

H-160
#B22T I IndividuaitUid*, teristics of Refabricated Fuel Rods

(Fresh FuAtJ'?radiated Cladding) under IGR Tests:-'

Table 11-9.8. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #B22T

Axial interval Energy deposition at infinite time Fuel enthalpy

from-to at time (t=4.78 s)

(mm)-(mm) caVg fuel Jig fuel per-unit cal/g fuel J/g fuel per-unit

10.5-24.7 110 460 1.00 78.7 330 1.00

24.7-38.9 106 443 0.96 75.7 317 0.96

38.9-53.1 103 433 0.94 74.0 310 0.94

53.1 - 67.3 102 427 0.93 73.1 306 0.93

67.3 -81.5 101 425 0.92 72.6 304 0.92

81.5-95.7 101 423 0.92 72.4 303 0.92

95.7- 109.9 101 422 0.92 72.2 303 0.92

109.9- 124.1 100 419 0.91 71.7 300 0.91

124.1 - 138.3 99.8 418 0.91 71.5 300 0.91

138.3 - 152.5 98.7 414 0.90 -70.7 296 0.90

120

100

C.

80

• 60

20

40

C.

~20

0)l

. .. . ... . . . .. .. ... . .. ... .

0

0 30 60 90

Axial coordinate (mm)

120 150 180

Fig. H-9.5. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6 Code

for Fuel Rod #B22T

H-161
#B22T Individual Characfcli[lcs ofRefabricated Fuel Rods

[(Fresh Fuel, Preifrai Cladding) under IGR Tests'- .'

1.2

C,

0

*0

1.0

0.8

0.6

0.4

0.2

1 2 3 4

Radial fuel coordinate (Mm)

100

80

a)

U

C.

C

60

40

20

0

1.0 1.5 2.0 2.5 3.0 3.5 4.0

Radial fuel coordinate (mm)

Fig. H-9.6. Radial Distributions of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #B22T

H-162
#B22T iidivi jzdu'&Adteristics of RefabricatedFuiel Rods -' I(Fresh Fuiirdiated Cladding) under IGR Tests

160

0ý

,.-

a-.

120

80

40

120

90 5

C;

60 -

*30 •

0.08

0.07

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

:' 1000

L3 800

E

iu 600

0.06'

4)

0

0.0542

0.04 "E

0.03o20

0.02.6

0.01

0.00

0 1 2 3 4 5 6' 7 8 9 10

Time (s)

Fig. H-9.7. Energy and Temperature Characteristics Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes for Fuel Rod #B22T

H-163
#B22T I Individual Cha ca et'jsebofRefabricated Fuel .Rods s

:(Fresh Fuel, Prei4;ia WdCladding) under IGR Tests .

2.5

2.0

2 1.5

LI

I..

0.5

0.0

15

12

0~

0.,

0

3

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

100

80

0.

0

60

40

FRAP-T6

.... SCANAIR

-- Clad hoop stra n

-0- Fuel- lad gap dth

2.5

2.0

EE

1.5 "S

1.0

0.5

0.0

20

0 g •l I i

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. H-9.8. Cladding Mechanical Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #B22T

.H-164

I I
#B22T I Jndividual.h'" eristicsofRefabricated Fuel Rods

.(Fresh ruet,%1 rdiated Cladding) under IGR Tests.

1.5

1.2

0.9

0

• 0.6

0.3

0.0

2000

1600

1200

E

q.

800

400

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. H-9.9. Fuel Strain Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel Rod #B22T

H-165
#B22T Ifidividual CthaiidýM st!gfRefabricated Fuel Rods'.

(Fish'Fuel,Prehj•YM 1adding) under IGR Tests

Table 11-9.9. Some Results of PIE for Fuel Rod #B22T

Characteristic Value

I. Measured parameters of cladding oxidation and cladding

deformation

1.1. Cladding thickness at elevation 35, 90 mm correspondent to

different azimuthal angles (pm):

00 425 663

900 R 649

1800 425 649

2700 677 677

1.2. ZrO2 thickness at elevation 35, 90 mm correspondent to different

azimuthal angles (pm):

00 5 5

900 5 5

1800 5 5

2700 5 5

1.3. ctZr(O) thickness at elevation 35, 90 mm correspondent to different

azimuthal angles (pm):

00 0 0

900 0 0

1800 0 0

2700 0 0

1.4. Clad hoop strain at elevation 35, 90 mm, respectively (%) 46.3 10.4

2. Measured parameters for FGR analysis

2.1. Internal gas composition (% by volume):

He

N2

02

Ar

C02

Kr

Xe

2.2. Free gas volume (cm 3

)

2.3. Gas pressure inside fuel rod under normal condition (MPa)

2.4. Kr concentration in fuel (cm3

/g fuel)"

3. Measured parameters of cladding hydriding'

3.1. Coefficient of hydride orientation (per-unit) 0.43

3.2. Hydrogen concentration (% by weight) _

H-166
#B22T lndividual •ja cristics of Refabrice Fuel Rods

(Fresh FueýI diated Cladding) under IGR Tests .

Table H-9.10. General Characteristic of Fuel Rod #B22T

Parameter Unit Value

Experiment FRAP-T6 SCANAIR

I Type of coolant air air air

2 Burnup MWd/kg U 0 0 0

3 Energy deposition in fuel rod cal/g fuel - 102 102 102

4 Peak fuel enthalpy cal/g fuel - 79 78

5 Peak fuel temperature K - 1523 1442

6 Peak clad temperature K - 1258 -

7 Fuel rod failure Yes, No Yes Yes -

8 Type of failure:

- cladding rupture due to ballooning Yes, No Yes Yes -

- cladding rupture due to PCMI Yes, No No No -

- fragmentation of fuel rod Yes, No No - -

9 Failure time s - 6.77 -

10 Fuel enthalpy at failure cal/g fuel - 77 -

11 Outer cladding temperature at failure K - 1258 -

12 Internal gas pressure at failure MPa - 1.94 -

13 ZrO2 thickness after test Pm 5 - -

14 Residual clad hoop strain:

- peak value for ballooning area % 46.3 58.86 -

- other location) % 10.4 0.89 -

')Calculated values by FRAP-T6 and SCANAIR codes are average along height of fuel rod excluding ballooning region

H-167

H-169

I -
#B23T .Jndividi~iaI CbA~~I~o~cfaricae ulRd'~,

1;( (l'~hFueýic add" [j~j gg) under IGR Tet

Fig. H-10.1. Appearance of Fuel Rod #B23T (photographs and X-ray photograph)

H-170
#B23T I IdivcfiAP~~h.4icof Rabricae ul os<

I(ro~~e:l!4ae Claddin-g) under IRTi~

ii'

422 t*0

Fig. H-10.2. Fuel Microstructure for Fragment of Fuel Rod NB23T

H-171

i ....
#B23T J ,Indtvid~iai M- RCfabincatedFuelRd -" I

if i Fuel.. n......... ... :

Table 11-10.1. Time Dependent Energy Characteristics of Fuel Rod #1B23T

Reactor Cumulative number of fissions Power of Energy deposition

Time energy in fuel rod (fiss) fuel rod in fuel rod

(s) deposi- 23 23 Total (kW) cal/g fuel Jg fuel

tiN X10,14 xl0"12 x10"14

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

9.0

10.0

20.0

30.0

0o

0.000

0.821

3.870

5.040

6.720

9.430

14.40

23.80

39.50

57.10

70.00

78.20

83.20

86.50

88.80

90.30

91.50

92.40

93.10

93.60

94.10

94.50

94.80

95.40

95.90

96.20

96.50

96.90

97.20

98.60

99.10

100.0

0.000

0.222

1.050

1.360

1.820

2.550

3.890

6.450

10.70

15.40

19.00

21.20

22.50

23A0

24.00

24.50

24.80

25.00

25.20

25.40

25.50

25.60

25.70

25.80

26.00

26.00

26.10

26.20

26.30

26.70

26.80

27.10

0.000

0.125

0.591

0.770

1.030

1.440

2.200

3.640

6.030

8.720

10.70

11.90

12.70

13.20

13.60

13.80

14.00

14.10

14.20

14.30

14.40

14.40

14.50

14.60

14.60

14.70

14.70

14.80

14.90

15.10

15.10

15.30

0.000

0.224

1.050

1.370

1.830

2.570

3.920

6.490

10.80

15.50

19.10

21.30

22.70

23.60

24.20

24.60

24.90

25.20

25.30

25.50

25.60

25.70

25.80

26.00

26.10

26.20

26.30

26.40

26.50

26.90

27.00

27.20

0.000

1.260

3.850

5.240

7.900

13.50

25.70

48.00

69.00

60.30

39.30

24.40

15.60

10.40

7.280

5.320

4.040

3.170

2.560

2.110

.1.760

1.490

1.280

0.905

0.682

0.544

0.454

0.385

0.305

0.077

0.040

0.000

0.000

2.550

12.00

15.60

20.80

29.30.

44.60

73.90

122.0

177.0

217.0

243.0

258.0

269.0

276.0

281.0

285.0

288.0

290.0

292.0

293.0

295.0

296.0

298.0

300.0

301.0

302.0

304.0

305.0

311.0

313.0

320.0

0.000

10.70

50.20

65.30

87.10

123.0

187.0

309.0

511.0

741.0

908.0

1017.

1080.

1126.

1155.

1176.

1193.

1206.

1214.

1222.

1226.

1235.

1239.

1247.

1256.

1260.

1264.

1273.

1277.

1302.

1310.

1340.

Maximum value of power is 702 kW (t - 3.25 s)

1) Current energy deposition per maximum energy deposition (at infinite time)

H-172
#B23T I 'of Rcfabric6ie Fuel Rods,'--,,ýý,'-ý-' I (lr ~ i~jedCIlding) under TGR Tests.:

Table 11-10.2. Axial Energy Characteristics of Fuel Rod #B23T

Axial Cumulative number of fissions Maximum Energy deposition

coordinate at axial interval (fiss) power of at infinite time*

from lower u235 U38 Total fuel cal/g fuel Jg fuel per-uni3)

end of fuel x(k-" X I x13 aW)

rod x10 " t3.25 - s

(mm)

20.0

25.01)

30.0

35.0

40.0

45.0

50.0

55.0

60.0

65.0

70.0

75.0

80.0

85.0

90.0

95.0

100.0

105.0

110.0

115.0

120.0

125.0

130.0

135.0

140.0

145.0

150.0

155.0

160.0

165.02)

170.0

0.000

3.550

10.30

10.20

10.10

9.980

9.840

9.750

9.670

9.670

9.610

9.580

9.560

9.580

9.570

9.490

9.370

9.360

9.480

9.480

9.470

9.400

9.460

9.500

9.480

9.500

9.480

9.320

9.100

7.830

0.000

0.000

1.730

5.110

5.150

5.220

5.260

5.260

5.300

5.340

5.400

5.440

5.470

5.490

5.550

5.570

5.560

5.500

5.510

5.580

5.580

5.580

5.530

5.550

5.560

5.530

5.520

5.470

5.350

5.200

4.440

0.000

0.000

3.570

10.40

10.20

10.20

10.00

9.890

9.800

9.720

9.730

9.660

9.640

9.610

9.640

9.620

9.550

9.420

9.420

9.530

9.530

9.530

9.460

9.520

9.550

9.540

9.560

9.540

9.380

9.160

7.870

0.000

0.000

0.920

2.680

2.640

2.630

2.590

2.550

2.530

2.510

2.510

2.490

2.490

2.480

2.490

2.480

2.460

2.430

2.430

2.460

2.460

2.460

2.440

2.460

2.460

2.460

2.470

2.460

2.420

2.360

2.030

0.000

0.000

348.0

345.0

339.0

338.0

333.0

329.0

326.0

324.0

323.0

321.0

319.0

3'18.0

318.0

317.0

316.0

316.0

316.0

317.0

315.0

316.0

314.0

316.0

313.0

313.0

313.0

312.0

310.0

309.0

306.0

0.000

0.000

1457.

1444.

1419.

1415.

1394.

- 1377.

1365.

1356.

1352.

1344.

1335.

1331.

1331.

1327.

1323.

1323.

1323.

1327.

1319.

1323.

1314.

1323.

1310.

1310.

1310.

1306.

1298.

1293.

1281.

0.000

0.00

1.00

0.99

0.97

0.97

0.96

0.95

0.94

0.93

0.93

0.92

0.92

0.91

0.91

0.91

0.91

0.91

0.91

0.91

0.91

0.91

0.90

0.91

0.90

0.90

0.90

0.90

0.89

0.89

0.88

0.00

All numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate ± 2.5 nun.

I) Initial coordinate of fuel is 25.8 mmn.

2) End coordinate of fuel is 166.8 nun.

3) Current value per maximum value.

H-173

I "I
#B23T Individugal ChM~?ofF~efabrica7ied Fuel Rý

ý,(Fresh tFu~hji icdding ae bRTet

Table 1H-10.3. Radial Energy Characteristics of Fuel Rod #B23T

Coordinates of fuel zones (mm)

Characteristics* I zone 2 zone 3 zone 4 zone

1.10- 2.12 2.12- 2.79 2.79-3.32 3.32-3.79

Number of fissions x 10-14 (fiss) 6.540 6.650 6.830 7.060

Power of fuel rod')(kW) 16.90 17.10 17.60 18.20

U235 Energy deposition 2

) (cal/g fuel) 308.0 313.0 321.0 332.0

Energy deposition 2

) (J/g fuel) 1289. 1310. 1344. 1390.

Energy deposition3

) (per-unit) 0.928 0.943 0.967 1.000

Number of fissions x10"12 (fiss) 3.840 3.810 3.810 3.810

Power of fuel rod') (kW) 0.098 0.097 0.097 0.097

U239 Energy deposition2) (cal/g fuel) 1.780 1.770 1.770 1.770

Energy deposition2) (J/g fuel) 7.450 7.410 7.410 7.410

Energy deposition3) (per-unit) 1.000 0.994 0.994 0.994

Number of fissions x 10-14 (fiss) 6.580 6.680 6.860 7.100

Power of fuel rod') (kW) 17.00 17.20 17.70 18.30

Total Energy deposition2) (cal/g fuel) 309.0 314.0 323.0 334.0

Energy deposition 2

) (J/g fuel) 1293. 1314. 1352. 1398.

1 Energy deposition 3

) (per-unit) 0.925 0.940 0.967 1.000

1) at time or3.25 s, 2) at infinite time, 3) Current value per maximum value

* All numerical values of characteristics were calculated for length of fuel stack

H-174
#B23T I (of Cdig Refabated n Fu Roest .,-

I ~Cliddingj) uinder IGR-Testsl.~

Table H-10.4. Fuel Enthalpy Vs. Time Calculated by FRAP-T6 Code for Fuel Rod #B23T

Time Enthalpy at fuel radius Fuel e ~ Energy deposition

i (eal/_ V fuel) _ Fuel nthalp _ ) in fuel rod

(s) 1.10 mnI 2.22mm I 2.89=mm 3.79n-n calg fuel Jig fuel cal/g fuel Jig fuel

0.0

1.0

2.0

2.2

2A

2.6

2.8

3.0

3.2

3A

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

2.34

11.3

14.8

19.9

28.4

44.0

74.6

127

190

240

270

269

268

0.00

2.32

11.1

14.6

19.6

28.0

43.6

74.1

126

188

237

266

270

270

0.00

2.27

10.7

14.1

19.0

27.1

42.2

71.8

122

179

219

247

261

264

0.00

2.08

9.63

12.5

16.7

23.3

34.9

54.5

78A

101

167

188

196

187

0.00

2.26

10.7

14.1

18.9

26.9

41.7

70.2

117

169

217

245

258

261

0.00

9.48

44.9

58.9

79.2

113

175

294

492

710

909

1027

1080

1094

0.00

2.54

12.0

15.6

20.8

29.3

44.6

73.9

122

177

217

242

258

269

276

281

285

288

290

292

293

295

296

298

300

301

302

305

313

0.00

10.7

50.3

65.5

87.3

123

187

310

513

741

910

1016

1083

1126

1156

1177

1193

1205

1215

1223

1229

1235

1240

1249

1255

1260

1265

1278

1312

Radial enthalpy distribution and fuel enthalpy are presented at elevation 32.9 mm

Maximum value of fuel enthalpy is 261.1 cal/g fuel (t--420 s)

1) All nurnccal values are presented at elevation %ith peak pover

H-175
#B23T Indivitdul &iiard-niOfRefabricated Fuel Rods'. ,

(Fresh Fuel,!Pre•eiqp Cladding) under IGR Tests

Table 11-10.5. Energy Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for

Fuel Rod #B23T

Energy Linear Clad-to-coolant heat

Time Ener Linear 1) Fuel enthalpy0 Leakage of energy trasfer coefficienti) (s)e deposition') pow~er') (agful el/ ul

(s) (cal/g fuel) (kW/m) (cal/g fuel) (cal/g fuel)(kW/m2K)

FRAP-T6I SCANAIR FRAP-T6 SCANAIR FRAP-T6_I SCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

2.72

12.8

16.7

22.3

31.3

47.7

79.0

131

189

232

259

276

287

295

300

304

307

310

312

314

315

316

318

320

321

323

326

335

0.00

9A2

28.8

39.2

59.1

101

192

359

516

451

294

182

117

77.7

54.4

39.8

302

23.7

18.9

15.6

13.1

11.0

9.49

6.72

5.07

4.05

3.39

2.27

0.30

0.00

2.26

10.7

14.1

18.9

26.9

41.7

70.2

117

169

217

245

258

261

0.00

2.47

11.2

14.5

19.3

27.1

41.6

69.1

113

0.00

0.00

0.01

0.01

0.01

0.02

0.03

0.05

0.10

024

0.88

1.82

320

5.35

0.00

0.00

0.01

0.01

0.01

0.02

0.03

0.06

0.12

0.00

0.01

0.01

0.01

0.01

0.01

0.02

0.02

0.04

0.07

0.09

0.11

0.14

0.20

0.00

0.01

0.01

0.01

0.01

0.01

0.02

0.02

0.05

L I L S I I S

I) All numnrical values arm presented at elevation v.ith peak powwr

H-176
#B23T Individu" teriics of Refabricated Fuel Rods

,(Fresh fi*Fj;: diated Cladding) under IGR Tests.-

Table 11-10.6. Temperature Variation, Fission Gas Release and ZrO2 Thickness Vs. Time for Fuel

Rod #B23T Calculated by FRAP-T6 and SCANAIR Codes

Time Fuel centerline Fuel surface Clad outer I1 (s) temperature') temperature1 ) temperatureS)

( ___(K) (K) (K)

FRAP-T6 FRANT6 I SP-P-T ___A____-6 I_ SCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

334

474

527

601

720

934

1335

1975

2581

2939

3111

3105

3105

293

333

468

518

587

696

889

1242

1798

293

329

450

493

554

649

810

1073

1384

1670

2384

2569

2631

2558

293

331

456

501

565

665

837

1128

1504

293

304

366

391

424

471

547

687

955

1267

1367

1517

1680

1899

293

305

373

400

436

488

574

736

1036

1) All numerical values are presented at elevation %ith peak powr

H-177
#B23T Individual C tiaiia ofReftabricated Fuel Rods

(Fresh Fuel, Preji cidCladding) undei IGR Tests ' .

Table 11-10.7. Mechanical Characteristics of Fuel Rod #B23T Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes

Time Clad outer Fuel hoop Fuel - clad gap Clad hoop Clad hoop Internal gas Tim temperature) strain') width') strain') stress') pressure

(S) (K) (%) (mm) (%) (MPa) (MPa)

FR"-T6 N ".T61ScaN FRP.APT6 SCANAId F•-T6 SCAN FT6 SCAN • F -.T6 1SCANAM

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

304

366

391

424

471

547

687

955

1267

1367

1517

1680

1899

293

305

373

400

436

488

574

736

1036

0.00

0.03

0.17

0.22

0.29

0.41

0.63

1.09

1.91

2.71

3.23

3.49

3.72

3.86

0.00

0.03

0.13

0.17

0.22

0.32

0.51

0.91

1.68

0.08 1 0.08 1 0.01 1 0.01 1 8.73 '.8.70 1.70 1 1.70

0.08

0.08

0.07

0.07

0.07

0.06

0.05

0.03

0.06

3.37

3.36

3.35

3.35

0.08

0.08

0.02

0.06

0.08 1 0.08

0.08 1 0.10

0.07

0.07

0.06

0.04

0.02

0.07

0.09

0.12

0.16

0.23

0.35

0.59

0.13

0.18

0.28

0.47

1.83

67.6

67.8

67.9

68.2

8.88

9.26

9.36

9.48

9.63

9.82

10.1

10.3

10.7

0.00

0.00

0.00

0.00

8.90

9.36

9.48

9.63

9.82

10.1

10.4

10.7

1.73

1.80

1.82

1.84

1.86

1.90

1.94

1.99

2.02

0.10

0.10

0.10

0.10

1.73

1.81

1.83

1.85

1.88

1.91

1.95

1.98

1) All numerical values are presented at elevation with peak pomr

H-178
#B23T .bdividualdRa""Scderistics of Refabriciated Fuel Rods: (FiishiU~AedV iated Cladding) under IGR Tests

Table H-10.8. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #B23T

Axial interval • Fuel enthalpy

from-to Energy deposition at infinite time at time (t=4.20 s)

(mm)-(mm) cal/g fuel J/g fuel per-unit cal/g fuel J/g fuel per-unit

25.8-39.9 342 1434 1.00 261 1094 1.00

39.9 - 54.0 332 1390 0.97 '253 1061 0.97

54.0-68.1 324 1357 0.95 250 1048 0.96

68.1-82.2 319 1338 0.93 245 1026 0.94

82.2-96.3 317 1329 0.93 245 1026 0.94

96.3-110.4 316 1325 0.92 245 1026 0.94

110.4 - 124.5 316 1322 0.92 245 1026 0.94

,124.5- 138.6 314 1317 0.92 243 1017 0.93

138.6- 152.7 313 1309 0.91 242 1014 0.93

152.7- 166.8 309 1293 0.90 238 998 0.91

350

•'300

Ca

'• 250

200

CE

150

S100

S50

0

20 40 60 80 100 120 140 160

Axial coordinate (mm)

180

Fig. H-10.3. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6 Code

for Fuel Rod #B23T

H-179
#B23T I -individualC dCh rade sofRefabricated Fuel Rods

(Fresh Fuel, Paii ATeSi Cladding) uinder IGR Tests, -

1.2

0

33

1.0

0.8

0.6

0.4

0.2

1 2 3 4

Radial fuel coordinate (mm)

300

250

_ 200

' 150

I.0

10

1o

0

- -. 0 0S

0--D-- 3,0s

-- O---4.2s

1.0 1.5 2.0 2.5 3.0 3.5 4.0

Radial fuel coordinate (mm)

Fig. H1-10.4. Radial Distributions of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6

Code for Fuel Rod #B23T

H-180
#B23T 1ndiiduhjcteristics of Refabricated Fuel Rods

(Fresh~ F•'I•if.fdiated Cladding) under IGR Tests

600

500

400

• 300

0

• 200 0

lO0

- FRAP-T6

.... SCANAIR

Power of fuel rod

Energy deposition

-0- Fuel enthalpy

• Leakage of energy

_ __~Clad oxidation _eriy

,I -

360

300

240

180

0.

120 •

60

0

0 1 2 3 4 5 6 7

Time (s)

8 9 10

3500

3000

2500

2000

E 1500

1000

500

0

0.21

0.18.

0.12~

0

0.03~

2

0.00

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. H-10.5. Energy and Temperature Characteristics Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes for Fuel Rod #B23T

H-181
#B23T Jn" 'dtdividual Cham a ucs.:ofRefabricamed Fuel Rods:*;

l(Fresh Fuel, Prse€ii Cladding) under IGR Tests,

2.5

2.0

0..

2 1.5

eO 1.0

0.5

0.0.

100

80

30

24

S

0.

18~

12

U,

6

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

0..

60

40

3.5

2.8

P

E

2.1 -5

1.4 --

LT.

0.7

0.0

20

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. H-10.6. Cladding Mechanical Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #B23T

H-182
#B23T lndfvdu erisiCs of Refabricated Fuel Rods

(Fresh F u~ a diated Cladding) under IGR Tests !

7

5

4

C0

- .,_ _- FRAP-T6

I... SCANAIR

, Fuel total hoop strain

r- Fuel centerline ternerature

3500

2800

2100 4

E

.-

1400

700

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. 11-10.7. Fuel Strain Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel Rod #B23T

H-183
#B23T Individafl Charaacfsii -of R'efabricated Fuel Rods 'i-

(Fresh Fuel, PreiAi=Cladding)uinder IGR Tests

Table 11-10.9. General Characteristic of Fuel Rod #B23T

Parameter Unit Value

Experiment FRAP-T6 SCANAIR

1 Type of coolant - air air air

2 Burnup MWd/kg U 0 0 0

3 Energy deposition in fuel rod cal/g fuel 320 320 320

4 Peak fuel enthalpy cal/g fuel - -

5 Peak fuel temperature K -

6 Peak clad temperature K -

7 Fuel rod failure Yes, No Yes Yes

8 Type of failure:

- cladding rupture due to ballooning Yes, No ? Yes

- cladding rupture due to PCMI Yes, No ? No

- fragmentation of fuel rod Yes, No Yes -

9 Failure time s 3.43

10 Fuel enthalpy at failure cal/g fuel 177

'11 Outer cladding temperature at failure K 1288

12 Internal gas pressure at failure MPa 1.72

13 ZrO2 thickness after test Pun m -

14 Residual clad hoop strain:

- peak value for ballooning area % -

- other location % -

lCalculated values by FRAP-T6 and SCANAIR codes are average along height of fuel rod excluding ballooning region

H-1 84
A.

I-1
lndividual C'l -J 'Refabric.lae'Fuel Rods #H C(Fresh Fuel:~rC~J 2~ underilGR Tests.---"

PositionWi] (900)

' 5 mm

Positionml (0

Fig. 1-1.1. Appearance of Fuel Rod #H6C (photographs and X-ray photograph)

1-2
#116 C ividu~~i~istcs of RefabricacdFelRd s

r 71

IL_)

Fig. 1-1.2. Cross-Section and Cladding Microstructure for Fuel Rod #116C at 90 mm Elevation

1-3
#H6C Individua d-a r :Refalrica ~n'iL ! Fuel Rods.'

S(Fresh Fuel, F nder IGR TestsI

LI

Position2

Fig. 1-1.3. Fuel Microstructure for Fuel Rod #H6C at 90 mm Elevation

1-4
#H6C [ Individ eristics ofRefabricated Fuel Rods* 'I

(Fresh F -Cladding) under'IGR Tests

Table 1-1.1. Time Dependent Energy Characteristics of Fuel Rod #H6C

Reactor Cumulative number of fissions Power of Energy deposition

Time energy in fuel rod (fiss) fuel rod in fuel rod

(s) deposi- 0235 U 23 8 Total (kW) cal/g fuel J/g fuel tiont) × 10"14 x 10"12 x 10"14

N%

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

9.0

10.0

20.0

30.0

0o

0.000

0.697

2.790

3.380

4.040

4.800

5.710

6.860

8.440

10.90

15.00

22.40

34.60

51.10

67.20

77.90

84.00

87.40

89.40

90.80

91.70

92.50

93.10

94.30

95.10

95.70

96.10

96.70

97.10

98.60

99.10

100.0

0.000

0.202

0.810

0.981

1.170

1.400

1.660

1.990

2.450

3.160

4.370

6.500

10.10

14.90

19.50

22.60

24.40

25.40

26.00

26.40

26.70

26.90

27.10

27.40

27.60

27.80

27.90

28.10

28.20

28.70

28.80

29.10

0.000

0.073

0.290

0.352

0.421

0.501

0.595

0.715

0.881

1.130

1.570

2.330

3.610

5.330

7.000

8.120

8.760

9.110

9.320

9.460

9.560

9.640

9.710

9.830

9.920

9.970

10.00

10.10

10.10

10.30

10.30

10.40

0.000

0.203

0.813

0.985

1.180

1.400

1.660

2.000

2.460

3.170

4.380

6.530

10.10

14.90

19.60

22.70

24.50

25.50

26.10

26.50

26.80

27.00

27.20

27.50

27.70

27.90

28.00

28.20

28.30

28.80

28.90

29.20

0.000

1.140

2.290

2.570

2.910

3.380

4.130

5.420

7.860

12.70

22.30

39.30

60.80

71.60

56.10

33.10

18.40

10.70

6.870

4.820

3.670

2.970

2.520

1.800

1.210

0.870

0.664

0.528

0.384

0.086

0.043

0.000

0.000

2.180

8.720

10.60

12.70

15.00

17.90

21.50

26.50

34.10

47.10

70.10

108.0

160.0

210.0

244.0

263.0

274.0

280.0

285.0

288.0

291.0

293.0

297.0

300.0

302.0

303.0

305.0

307.0

314.0

316.0

323.0

0.000

9.130

36.50

44.40

53.20

62.80

74.90

90.00

111.0

143.0

197.0

293.0

452.0

670.0

879.0

1021.

1101.

1147.

1172.

1193.

1206.

1218.

1226.

1243.

1256.

1264.

1268.

1277.

1285.

1314.

1323.

1352.

Maximum value of power is 71.6 kW (t - 4.20 s)

1) Current energy deposition per maximum energy deposition (at infinite time)

I-5
#H6C Individtial'Ch'l of Refabricatcd Fuel Rods' I

1,7(Fresh Fuel, Fresiiq~r~jiii) under IGR TestsI

Table 1-1.2. Axial Energy Characteristics of Fuel Rod #H6C

Axial Cumulative number of fissions Maximum Energy deposition

coordinate in fuel rod (fiss) power of at infinite time*

from lower u235 U238 Total fuel rod cal/g fuel J/g fuel per-unit 3

)

end of fuel x10-" X10-1 x10-13 (kW)

rod t=4.20 s

(mm)

15.0 0.00 0.00 0.00 0.00 0.00 0.00 0.00

25.0:) 13.70 4.070 13.70 3.380 362.0 1515. 1.00

35.0 22.00 7.040 22.10 5.430 350.0 1465. 0.97

45.0 21.20 7.270 21.20 5.220 338.0 1415. 0.93

55.0 20.80 7.520 20.90 5.130 329.0 1377. 0.91

65.0 20.30 7.600 20.40 5.010 321.0 1344. 0.89

75.0 20.10 7.690 20.20 4.960 316.0 1323. 0.87

85.0 19.70 7.620 19.80 4.870 313.0 1310. 0.86

95.0 19.50 7.530 19.60 4.810 311.0 1302. 0.86

105.0 19.60 7.500 19.70 4.840 310.0 1298. 0.86

115.0 19.70 7.410 19.80 4.870 311.0 1302. 0.86

125.0 19.60 7.210 19.70 4.840 313.0 1310. 0.86

135.0 20.00 7.180 20.10 4.940 316.0 1323. 0.87

145.0 20.40 7.120 20.40 5.020 319.0 1335. 0.88

155.0 20.60 7.040 20.60 5.070 323.0 1352. 0.89

165.02) 13.20 4.460 13.30 3.260 326.0 1365. 0.90

175.0 0.00 0.00 0.00 0.00 0.00 0.00 0.00

All numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate " 5.0 mnm

1) Initial coordinate of fuel is 24.0 mm

2) End coordinate of fuel is 168.0 mm

3) Current value per maximum value

1-6

I -
#H6C I lnd~uafi efristcs of Refabrine ulRd I Feh lading) under IGR Tests -

Table 1-1.3. Radial Energy Characteristics of Fuel Rod #H6C

Coordinates of fuel zones (mm)

Characteristics* I zone 2 zone 3 zone 4 zone

1.10-2.14 2.14-2.83 2.83 -3.37 3.37-3.84

Number of fissions x10" (fiss) 6.930 7.190 7.240 7.690

Power of fuel rod') (kM) 17.00 17.70 17.80 18.90

U735 Energy deposition2) (cal/g fuel) 308.0 314.0 324.0 340.0

Energy deposition2

) (J/g fuel) 1289. 1314. 1356. 1423.

I Energy deposition3) (per-unit) 0.906 0.924 0.953 1.000

Number of fissions x10-12 (fiss) 2.570 2.680 2.590 2.580

Power of fuel rod') (kW) 0.062 0.065 0.063 0.063

U2 8 Energy deposition (ca gfuel) 1.130 1.150 1.140 1.130

Energy deposition2) (J/g fuel) 4.730 4.810 4.770 4.730

Energy deposition3) (per-unit) 0.983 1.000 0.991 0.983

Number of fissions x10"14.(fiss) 6.960 7.220 7.270 7.710

Power of fuel rod') (kW) 17.10 17.70 17.90 19.00

Total Energy deposition2) (cal/g fuel) 309.0 315.0 325.0 341.0

Energy deposition 2

) (J/g fuel) 1293. 1319. 1360. 1427.

Energy deposition3) (per-unit) 0.906 0.924 0.953 1.000

!) at time of"4.20 s, 2) at infinite time, 3) Current value per maximum value

All numerical values of characteristics were calculated for length of fuel stack

1-7
#H6C Individual Chaak. 6fRefabricated Fuel Rods

(Fresh Fuel,:Fie4 g) nder IGR Tests

Table 1-1.4. Fuel Enthalpy Vs. Time Calculated by FRAP-T6 Code for Fuel Rod #I16C

Time Enthalpy at fuel radius Fuel --"l )Energy deposition

T 1iome (Lca fuel) enthalpy in fuel rod

(S) 1.10mmI 2.20mm I 2.93mm I 3.79mm calfg fuel JIg flkI calfgfel _Jg fuel

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5A

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

2.20

8.38

10.1

12.0

14.2

16.9

20.2

24.9

32.3

45.3

68.7

107

158

207

241

259

268

269

269

268

269

268

262

253

243

233

189

19.5

0.00

2.17

8.22

9.90

11.8

13.9

16A

19.6

24.0

31.2

43.9

66.9

105

155

201

232

247

253

255

255

253

251

248

240

231

221

211

166

19.2

0.00

2.08

7.85

9.45

11.2

13.1

15.3

18.0

22.0

28.4

39.8

60.6

93.5

134

173

197

211

217

218

217

215

211

208

199

191

182

173

130

18.5

0.00

1.83

6.98

8.37

9.69

11.0

12.4

14.1

16.5

20.0

25.3

34.7

32.6

50.6

77.9

128

142

145

146

145

144

142

140

136

131

127

122

89.5

17.5

0.00

2.07

7.84

9.43

11.2

13.0.

152

17.9

21.8

28.0

38.8

58.4

86.6

126

165

196

212

218

219

219

217

214

211

204

196

187

179

138

18.6

0.00

8.67

32.8

39.5

46.8

54.6

63.7

75.1

91.3

117

163

245.

363

527

691

821

887

913

919

916

908

898

886

855

821

785

750

576

78.0

0.00

2.14

8.58

10.4

12.5

14.8

17.6

21.2

26.2

33.9

47.1

70.2

108

158

206

239

258

270

276

281

285

287

290

294

298

300

301

305

316

0.00

8.97

36.0

43.6

52.2

62.1

73.9

89.0

110

142

197

294

452

660

861

1002

1083

1129

1158

1178

1193

1205

1214

1233

1247

1256

1262

1279

1326

Radial enthadpy distribution and fuel entmlpy are prsented at elevation 31.2 mrn

Mwdnm value of fuel enthalpy is 219.4 cal/g fuel (t=5.20 s)

1-8
#H6C Inaividuu-i sctics bf Refabr'icte Fuel Rods (Fresh Fue7; ,• Cladding) Uinder IGRTests ',! ,. [:• ! •I

Table 1-1.5. Energy Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel

Rod #H6C

Energy Linear 1 Energy of Clad-to-coolant heat

Tim deposition Fuel enthalpy') metal-water Leakage of energy') transfer coefficienti)

(s) c(al/g fel) (cal/g fuel) reaction' cal/g fuel) (kW/mK)

FRAP-T6 I SCANAIR FRAP-T6 FRAP-T6_I SCANAIR FRAP-T6 ISCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0,

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

2.33

9.33

11.3

13.6

16.1'

192

23.1

28.5

36.9

512

76.4

117

171

224

260

281

293

300

305

309

312

314

319

323

325

327

331

343

0.00

8.54

17.2

19.3

21.8

25.3

30.9

40.6

58.9

95.2

167

294

456

536

420

248

138

80.2

51.5

36.1

27.5

22.3

18.9

13.5

9.07

6.52

4.97

2.88

0.32

0.00

2.07

7.84

9.43

11.2

13.0

15.2

17.9

21.8

28.0

38.8

58.4

86.6

126

165

196

212

218

219

219

217

214

211

204

196

187

179

138

18.6

0.00

2.00

7.85

9.26

11.0

12.9

14.7

17.4

21.3

26.6

37.2

56.6

84.8

128

.0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00.

0.02

0.10

0.27

0.54

0.87

1.21

1.52

1.80

2.31

2.64

2.83

2.95

2.97

2.97-

0.00

0.00

0.02

0.11

0.50

1.11

1.94

3.02

4.45

6.46

9.56

14.7

25.9

34.1

36.9

41.1

45.6

50.4

55.6

61.0

66.5

72.1

77.7

91.5

105

117

129

202

342

0.00

0.01

0.08

0.26

0.80

1.57

2.42

3.70

5.40

7.41

10.9

17.3

28.3

32.8

0.00

0.03

0.03

0.87

1.71

2.32

2.98

3.81

4.97

6.92

10.7

15.9

26.9

1.05

135

1.40

1.42

1.46

1.48

1.50

1.50

1.51

1.51

1.49

1.47

1.44

1.68

10.8

1.04

0.00

0.10

0.10

1.38

2.17

2.88

3.56

4.56

6.06

8.17

12.7

22.2

28.4

1.46

1 1 1 A. I I A. A.

1) All numerical values ame presented at elevation %ith peak poer

1-9
#1 .6C I ndividual ChamracfsiiofRefabricated Fuel Rods #H % (Fresh Ftlel,FVri&T..;Q'g) under IGR Tests !i. ff .

Table 1-1.6. Temperature Variation, Fission Gas Release and ZrOj Thickness Vs. Time for Fuel

Rod #H6C Calculated by FRAP-T6 and SCANAIR Codes

Fuel centerline Fuel surface Clad outer Average

Time temperature" temperature1) temperature t) ZrO2 

2 )

(s) (K) (K) (K). thickness

"FRAP-T6 SCANAIR FRAP-T6 SCANAIR FRAP-T6 SCANAIR FRAP-T6

0.0

1.0

2.0

2.2.

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

331

430

457

486

519

557

605

671

775

952

1259

1742

2301

2716

2944

3053

3103

3105

3105

3105

3105

3105

3067

3015

2955

2890

2577

595

293

325

418

441

469

501

532

577

640

720

877

1159

1577

2139

293

325

409

430

451

470

491

517

551

602

677

808

779

1021

1377

1984

2135

2172

2177

2169

2155

2138

2121

2074

2024

1972

1920

1525

567

293

324

408

427

446

466

484

510

548

597

686

802

867

1252

293

308

370

384

389

392

394

397

400

405

413

421

447

792

1168

1239

1278

1331

1371

1397

1410

1415

1412

1386

1347

.1305

1258

413

385

293

308

372

380

382

384

385

387

390

393

398

408

441

1014

5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.00

5.01

5.04

5.10

5.19

5.32

5.50

5.70

5.90

6.09

6.49

6.76

6.94

7.05

7.07

7.07

1) All numerical values are presented at elevation with peak power

2) Initial ZrO( thickness is 5 tan

1-10
#H6C (Fresh - M eiis under I Individu'l cterists of Refabricated Fue Rods -- (Feh uAR Cladding) under IGR Tests •:i•,:" •

Table 1-1.7. Mechanical Characteristics of Fuel Rod #H6C Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes

Clad outer Fuel hoop Fuel - clad gap Clad hoop Clad hoop Internal gas (s) temperature) strain' width1) strain) stress1 ) pressure

(K) (%) (MM) M%) (MPa) (MPa)

FRAP-T6 SCANAIR FRAP-T6 SCANAIR FRAP-T61SCANAIIj FRAP-T61SCANAIMI FRAP.T61SCANAIM FRAP.T6TSCANA]I

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

308

370

384

389

392

394

397

400

405

413

421

293

308

372

380

382

384

385

387

390

393

398

408

441

1014

447

792

1168

1239

1278

1331

1371

1397

1410

1415

1412

1386

1347

1305

1258

413

385

0.00

0.00

0.04

0.07

0.10

0.13

0.17

0.22

0.29

0.39

0.57

0.91

1.48

2.26

2.95

3.40

3.73

3.89

3.90

3.90

3.88

3.85

3.82

3.69

3.47

3.32

3.20

2.56

0.23

0.00

0.02

0.09

0.11

0.13

0.15

0.17

0.20

0.25

0.31

0.45

0.72

1.14

1.91

0.03 1 0.03 0.01 1 0.01 10.3

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.02

0.02

0.01

0.00

0.00

0.00

0.00

0.52

0.50

0.50

0.50

0.50

0.50

0.50

0.50

0,51

0.51

0.52

0.52

0.55

0.64

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.03

0.02

0.02

0.01

0.00

0.00

0.02

0.06

0.07

0.08

0.08

0.08

0.09

0.09

0.10

0.11

0.13

0.54

1.16

1.67

15.1

15.1

15.1

15.2

15.2

15.2

.15.2

15.2

15.2

15.2

15.1

15.1

14.9

14.8

0.02

0.07

0.08

0.08

0.08

0.09

0.09

0.10

0.10

0.12

0.15

0.29

0.95

10.5

10.7

10.7

10.8

10.8

10.9

10.9

11.0

11.1

11.2

11.3

205

127

12.2

0.00

0.00.

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

10.5

10.8

10.9

11.0

11.1

11.2

11.3

11.5

11.8

12.3

13.2

124

.30.5

2.02

2.06

2.07

2.08

2.09

2.10

2.11

2.12

2.14

2.16.

2.18

2.20

2.22

2.23

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

10.4 1 2.00 2.00

2.02

2.06

2.07

2.08

2.09

2.10

2.11

2.12

2.13

2.15

2.18

2.20

2.21

41

1) All numerical values are presented at elevation with peak povr

1-11
#H6C Individual~ai Ch"radtc-1-bfRefabricated Fuel Rods I

(Fresh Fuel'iJre~i~ i under IGR Tests -

Table 1-1.8. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6 Code

for Fuel Rod #H6C

Axial interval Energy deposition at infinite time Fuel enthalpy

from-to at time (t=5.20 s)

(mm)-(mm) caVg fuel JMg fuel per-unit ca!/g fuel J/g fuel per-unit

24.0-38.4 350 1467 1.00 219 919 1.00

38.4-52.8 335 1402 0.96 210 878 0.96

52.8-67.2 324 1359 0.93 203 851• 0.93

67.2-81.6 315 1320 0.90 197 827 0.90

81.6-96.0 313 1311 0.89 196 821 0.89

96.0-110.4 313 1311 0.89 196 821 0.89

110.4 - 124.8 313 1311 0.89 196 821 0.89

124.8- 139.2 317 1330 0.91 199 833 0.91

139.2- 153.6 323 1353 0.92 202 847 0.92

153.6- 168.0 326 1368 0.93 204 857 0.93

400

350

, 300

"5 250

200

.~150

"0

100

150

0

20 40 60 80 100 120

Axial coordinate (mm)

140 160 180

Fig. 1-1.4. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6 Code

for Fuel Rod #H6C

1-12
#H6C [ Iindivid•ix•at i-icteristics of Refabricatied Fuel Rods ,' .

I (Fresh Ftull.~1-Cladding) under IGR Tests

1.2

rn

C".

0

1.0 -f t I

0.8+-

0.6 -j7r7 777

:r :,,,ýý,ý

Ii, 7

0.4 -

0.2-

S

IV

2 ~1~~~

2

I 3

3 I 4

Radial fuel coordinate (mm)

300

250

4= 200

150

W 100

50

0

--- 0---.O

-•m0 - 21- s .0 s

-=. .= 5.2s

1.0 1.5 2.0 2.5 3.0 3.5 4.0

Radial fuel coordinate (mm)

Fig. 1-1.5. Radial Distributions of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6 Code

for Fuel Rod #H6C

1-13
#H6C Indiividial C'haradc-sof Refabricated Fuel Rods .

I(Fresh Fu el, ýFresýi tffg) under IGR Tests I

600

500

400

• •300 0

I_-

0 200

100

0

360

300

240

ISO

C)

180 .

120 •

60

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

3500

3000

2500

2000

"' 1500

1000

500

____I ____ I -1 ,4 ____ ___ __ I ____

35

I I

111__1iv

I- K . FRAP-T6 -

SCANAIR

Fuel centerline temperature

Clad outer temperature

Heat transfer coefficient -1 * I

II.1

Ii

: I

30

4)

25 0

20 P

15.

0

U

106

o

5

* El.

.11.

.11-

.11'

.1I*

'II-.

I

0 A S 0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. 1-1.6. Energy and Temperature Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #H6C

1-14
#H6C rIndievid u .aC&cteristics of Rierbricated Fuel Rods. I(Fresh FO*T Cladding) under IGR Tests

2.5 250l

- 200

J

2.0 .51~-4 I 4 + -I 4

o 1.5

a.-

- 1.0

E

0.5

0.0

18

15

12

S9

0

0

* 11

* - FRAP-T6 .... SCANAIR 1

, -- Internal gas pressure

,,-O - Clad hoop stress

5•

r0

0 1 2 3 4 5 6 .7 8 9 10"

Time (s)

10

5e

50

00

0

.60

_.__ "--_ _ _• 0.50

__I ___ L I_ IIL40

.1. 4 4 4-4-4 4 4 4

v

FRAP-T6

.... SCANAIR

IClad hoop stra n

Fuel- lad gap dth

0*0

0.30

020

0.20 "•

0.10

0.00

3 4 + 4 4-I-i I

/ 1 4' a- a a a a a a

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. 1-1.7. Cladding Mechanical Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR

Codes for Fuel Rod #H6C

1-15
#H6C -ndividu•l Charmalcof Refabricated Fuel Rods I

I(Fresh Fuel, Fresý,-137dg under IGR Tests~ ', -.

5.0

4.0

3.0

0

2.0

1.0

0.0

3500

2800

2100

1400

•700

0

0 1 2 3 4 5 6 7 8 9 10

Time (s)

Fig. 1-1.8. Fuel Strain Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel Rod #116C

1-16
[ individ alSa. ristics of Refab~ricatW F Iuei.Rods,.i':,•: #H6C I(Frsh FRodladdg)uder IGR Tests

Table 1-1.9. Some Results of PIE for Fuel Rod #H6C

Characteristic Value

1. Measured parameters of cladding oxidation and cladding

deformation

1.1. Cladding thickness at elevation 90 mm for different azimuthal

angles (pm):

00 610

900 R

1800 570

2700 340

1.2. ZrO2 thickness at elevation 90 mm for different azimuthal angles

(Prm):

00 5

900 5

1800 5

2700 5

1.3. aZr(O) thickness at elevation 90 mm for different azimuthal angles

(0m):

00 0

900 0

1800 0

2700 0

1.4. Clad hoop strain at elevation 90 mm (%) 23.5

2. Measured parameters for FGR analysis

2.1. Internal gas composition (% by volume):

He

N2

02

Ar

C0 2

iKr

Xe

2.2. Free gas volume (cm3

)

2.3. Gas pressure inside fuel rod under normal condition (MPa)

2.4.1 Kr concentration in fuel (cm 3

/g fuel)

3. Measured parameters of cladding hydriding

3.1. Coefficient of hydride orientation (per-unit)

3.2. Hydrogen concentration (% by weight)

1-17
#H6C Iindividtial ChraLrnd i of Refabricated Fuel Rods[

(Freish Fuel, Fres*7 ng) under IGR Tests :

Table I-1.10. General Characteristic of Fuel Rod #116C

Parameter Unit Value

Experiment FRAP-T6 SCANAIR

1 Type of coolant - water water water

2 Burnup MWd/kg U 0 0 0

3 Energy deposition in fuel rod cal/g fuel 323 323 323

4 Peak fuel enthalpy cal/g fuel - 219

5 Peak fuel temperature K - 3121

6 Peak clad temperature K - 1415

7 Fuel rod failure Yes, No Yes Yes

8 Type of failure:

- cladding rupture due to ballooning Yes, No Yes Yes

- cladding rupture due to PCMI Yes, No No No

- fragmentation of fuel rod Yes, No No -

9 Failure time s - 4.54

10 Fuel enthalpy at failure cal/g fuel - 187

11 Outer cladding temperature at failure K - 1241

12 Internal gas pressure at failure MPa - 2.24

13 ZrO2 thickness after test Pin 5 7.07

14 Residual clad hoop strain:

- peak value for ballooning area % 23.5 14.77 -

- other location)% - 1.82

"Calculated values by FRAP-T6 and SCANAIR codes are average along height of fuel rod excluding ballooning region

1-18
1-19
#B20C [ Iidivid,•ai Chac f kRe fabrikated Fuel Rods

(Fresh Fuel, Fr . ng) under IGR Tesfs A- I

PositionE-J (900)

Fig. 1-2.1. Appearance of Fuel Rod #B20C (photographs and X-ray photograph)

1-20
#B20C I :Indivj~d~w0 Rledstics of Refabricated Fuel Rods :9 I

*(Fresh Ftunder adding) IGR Tests

Fig. 1-2.2. Cross-Section and Cladding Microstructure for Fuel Rod #B20C at 55 mm Elevation

1-21
#B20C Individu~i i r oRcfabricated Fuel Rods -

(Fresh Fuel F digunder IGR ITests -~

Fig. 1-2.3. Cross-Section and Cladding Microstructure for Fuel Rod #B20C at 90 mm Elevation

1-22
#B20C I ndivdualF eristics of Refabricated Fuel Rods,

(Fresh Cladding) under IGRTests

-M

Fig. 1-2.4. Fuel Microstructure for Fuel Rod #B20C at 90 mm Elevation

1-23
#B20C Individual Char nMMs of Refabricated Fuel Rods

I(Fresh Fuel, FrcshI&d~ig) under IGR Tests I

Table 1-2.1. Time Dependent Energy Characteristics of Fuel Rod #B20C

Reactor Cumulative number of fissions Power of Energy deposition

Time energy in fuel rod (fiss) fuel rod in fuel rod

(s) deposi- 238al cal/g fuel J/g fuel

tinX0 x1 0"14 xT0o1t X10141

_________ (%) _____

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

9.0

10.0

20.0

30.0'

00O

0.000

0.515

2.060

2.490

2.970

3.480

4.040

4.640

5.340

6.190

7.300

8.910

11.50

16.00

24.00

36.90

53.20

68.10

78.30

84.40

87.90

90.00

91.40

93.50

94.80

95.70

96.30

97.10

97.70

99.30

99.80

101.0

0.000

0.071

0.283

0.342

0.407

0.477

0.554

0.637

0.734

0.850

1.000

1.220

1.580

2.190

3.300

5.060

7.300

9.340

10.80

11.60

12.10

12.40

12.50

12.80

13.00

13.10

13.20

13.30

13.40

13.60

13.70

13.80

0.000

0.040

0.162

0.195

0.233

0.273

0.317

0.364

0.419

0.486

0.573

0.699

0.900

1.250

1.880

2.890

4.170

5.340

6.140

6.620

6:890

7.060

7.170

7.330

7.440

7.510

7.550

7.620

7.660

7.790

7.830

7.900

0.000

0.071

0.284

0.344

0.409

0.480

0.557

0.641

0.738

0.855

1.010

1.230

1.580

2.210

3.320

5.090

7.340

9.400

10.80

11.60

12.10

12.40

12.60

12.90

13.10

13.20

13.30

13.40

13.50

13.70

13.80

13.90

0.000

0.399

0.800

0.880

0.960

1.040

1.120

1.260

1.480

1.850

2.530

3.830

6.440

11.60

20.10

29.40

32.00

24.80

15.40

8.860

5.250

3.360

2.350

1.320

0.924

0.616

A0435

0.324

0.213

0.042

0.021

*0.000

0.000

0.805

3.220

3.900

4.640

5.450

6.320

7.280

8.380

9.710

11.40

14.00

18.00

25.00

37.60

57.80

83.20

107.0

123.0

132.0

138.0

141.0

143.0

147.0

149.0

151.0

152.0

153.0

154.0

158.0

159.0

163.0

0.000

3.370

13.50

16.30

19.40

22.80

26.50

30.50

35.10

40.60

47.70

58.60

75.30

105.0

157.0

242.0

348.0

448.0

515.0

553.0

578.0

590.0

599.0

615.0

624.0

632.0

636.0

640.0

645.0

661.0

666.0

682.0

Maximum value ofpower is 32.4 kW (t - 4.75 s)

1) Current energy deposition per maximum energy deposition (at infinite time)

1-24
#B20C -lfdiiIduýýiJhmeristics of Refabricated iFue Rods

I(Fresh Fudel,' Cladding) under IGR Tests -

Table 1-2.2. Axial Energy Characteristics of Fuel Rod #B20C

Axial Cumulative number of fissions Maximum Energy deposition

coordinate in fuel rod (fiss) power of at infinite time*

from lower U235 U23

8 Total fuel rod cal/g fuel J/g fuel per-unit3)

end of fuel X10 . 3 Xl0- 1 1 x10-" (kW)

rod l t4.75

(mm)

20.0

25.0')

30.0

35.0

40.0

45.0

50.0

55.0

60.0

65.0

70.0

75.0

80.0

85.0

90.0

95.0

100.0

105.0

110.0

115.0

120.0

125.0

130.0

135.0

140.0

145.0

150.0

155.0

160.0

165.02)

170.0

0.000

3.550

5.050

5.040

5.070

5.040

4.990

4.970

4.940

4.960

4.940

4.910

4.890

4.850

4.840

4.750

4.720

4.740

4.790

4.790

4.750

4.750

4.750

4.760

4.780

4.790

4.800

4.800

4.800

3.400

0.000

0.000

1.770

2.590

2.660

2.750

2.790

2.820

2.850

2.870

2.900

2.910

2.910

2.910

2.890

2.880

2.830

2.800

2.800

2.820

2.800

2.770

2.750

2.740

2.730

2.720

2.720

2.720-

2.710

2.700

1.910

0.000

0.000

3.570

5.080

5.060

5.100

5.070

5.020

5.000

4.970

4.990

4.970

4.940

4.920

4.870

4.870

4.780

4.750

4.760

4.820

4.810

4.780

4.780

4.780

4.790

4.810

4.820

4.830

4.830

4.830

3.410

0.000

0.000

0.832

1.180

1.180

1.190

1.180

1.170

1.170

1.160

1.160

1.160

1.150

1.150

1.140

1.130

1.110

1.110

1.110

1.120

1.120

1.110

1.110

1.110

1.120

1.120

1.120

1.130

1.120

1.120

0.796

0.000

0.000

170.0

170.0

168.0

168.0

167.0

166.0

166.0

164.0

164.0

164.0

162.0

162.0

162.0

162.0

160.0

160.0

160.0

160.0

160.0

159.0

159.0

159.0

159.0

160.0

161.0

161.0

161.0

163.0

164.0

0.000

0.000

712.0

712.0

703.0

703.0

699.0

695.0

695.0

687.0

687.0

687.0

678.0

678.0

678.0

678.0

670.0

670.0

670.0

670.0

670.0

666.0

666.0

666.0

666.0

670.0

674.0

674.0

674.0

682.0

687.0

0.000

0.00

1.00

1.00

0.99

0.99

0.98

0.98

0.98

0.96

0.96

0.96

0.95

0.95

0.95

0.95

0.94

0.94

0.94

0.94

0.94

0.94

0.94

0.94

0.94

0.94

0.95

0.95

0.95

0.96

0.96

0.00

All numerical values of characteristics are presented as average values at the length interval equal to the axial coordinate :t 2.5 nmm.

1) Initial coordinate of fuel is 24.0 mm.

2) End coordinate of fuel is 166.0 mm.

3) Current value per maximum value.

1-25
#B20C Tndisidual Chira•.istdg)ufRefabricaG Fue Rods ' I

I(reshf FelFrfldiig under JGR Tests .:

Table 1-2.3. Radial Energy Characteristics of Fuel Rod #B20C

Coordinates of fuel zones (mm)

Characteristics* I zone 2 zone 3 zone 4 zone

1.10-2.12 2.12-2.78 2.78-3.32 3.32-3.78

Number of fissions x10"14 (fiss) 3.330 3.380 3.480 3.620

Power of fuel rod') (kM) 7.770 7.880 8.120 8.440

U235 Energy deposition2) (cal/g fuel) 156.0 158.0 163.0 170.0

Energy deposition2) (J/g fuel) 653.0 661.0 682.0 712.0

Energy deposition3) (per-unit) 0.918 1.0.929 0.959 1.000

Number of fissions x 10-12 (fiss) 2.000 1.990 1.970 1.940

Power of fuel rod') (kW) 0.046 0.046 0.045 0.045

U238 Energy deposition2) (cal/g fuel) 0.923 0.919 0.909 0.898

Energy deposition2) (J/g fuel) 3.860 3.810 3.760

Energy deposition3) (per-unit) 1.000 0.996 0.985 0.973

Number of fissions xI0"14 (fiss) 3.350 3.400 3.500 3.640

Power of fuel rod') (kW) 7.820 .7.930 8.170 8.490

Total Energy deposition 2

) (cal/g fuel) 157.0 159.0 164.0 170.0

Energy deposition 2

) (J/g fuel) 657.0 666.0 687.0 712.0

1 Energy deposition3) (per-unit) 0.924 0.935 0.965 1.000

at time cf4.75 s, 2) at infinite time, 3) Current value per maximum value

All numerical values of characteristics were calculated for length of fuel stack

1-26

I -
#B20C lInidi•idatl c erIstics of Refabricited Fuel Rods:

J(Frish Fue i-1f Cladding) trider IGR Teits,

Table 1-2.4. Fuel Enthalpy Vs. Time Calculated by FRAP-T6 Code for Fuel Rod #B20C

Enthalpy at fuel radius F t ) Energy deposition Time (cal/& fuel) Fuel enthalpy in fuel rod

(s) 1.10mm 2.22mm I 2.89mm I 3.79mm cal'gfuel i/gfuel cal/gfucl JI gfucl

0.0

1.0

2.0

22

2A

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4A

4.6

4.8

5.0

52

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

0.71

2.78

3.36

3.99

4.68

5.42

624

7.19

8.36

9.92

12.2

16.1

23.0

35.4

55.5

81.4

106

122

132

137

139

140

138

135

132

130

122

87.4

0.00

0.71

2.75

3.32

3.94

4.62

5.35

6.15

7.09

8.24

9.79

12.1

15.9

22.8

35.1

55.2

80.8

104

120

128

131

132

131

130

129.

127

126

120

86.7

0.00

0.70

2.68

3.23

3.84

4.50

5.21

5.99

6.90

8.03

9.54

11.8

15.5

22.2

34.3

53.8

78.1

99.3

112

117

117

118

119

120

120

120

119

116

85.6

0.00

0.65

2.50

3.01

3.58

4.19

4.86

5.59

6.43

7A7

8.86

10.9

14.2

19.9

29.7

43.9

59.2

70.9

78.0

81.2

90.0

99A

103

107

108"

109

110

109

83.5

0.00

0.70

2.68

3.24

3.84

4.50

5.22

6.00

6.91

8.04

9.55

11.8

15.5

22.1

34.0

52.9

76.2

96.8

110

115

118

121

122

123

123

122

121

117

85.8

0.00

2.92

11.2

13.6

16.1

18.9

21.9

25.1

29.0

33.7

40.0

49.4

64.9

92.6

142

221

319

405

459

484

496

507

513

516

515

510

0.00

0.80

3.22

3.90

4.64

5A5

6.32

7.28

8.38

9.71

11.4

14.0

18.0

25.1

37.6

57.8

83.2

107

123

132

138

141

143

147

149

151

0.00

3.37

13.5

16.3

19.5

22.8

26.5

30.5

35.1

40.7

48.0

58.5

75A

105

158

242

349

447

514

554

577

592

601

616

624

632

635

647

667

507

489

359

152

154

159

Radial enthalpy distribution and fuel enthalpy are presented at elevation 31.1 nmn

MaWximum value of fuel enthalpy is 123.2 cal'g fuel (t=6.50 s)

1 All nureical values are presented at elevation %ith peak pomr

1-27
#B20C I lndividual 6karct WofRefabricated Fuel Rods.

I(Fresh Fuel, Frýhýjgo'dng) under IGR Tests I

Table 1-2.5. Energy Characteristics Vs. Time Calculated by FRAP-T6 and SCANAIR Codes for Fuel

Rod #B20C

T Energy Linear 1) Clad-to-coolant heat Time depositioni) power') Fuel enthalpy') Leakage of energy transfer coefficient]) (s) (cal/g fuel) (kW/m) (ca/g fuel) (caYg fuel) (kW/m2K)

FRAP-T6 I FRAPT6 IJSCANAIR SCANAIR FRAP-T6 

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

.5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

0.00

0.84

3.35

4.06

4.83

5.67

6.57

7.57

8.71

10.1

11.9

14.5

18.7

26.1

39.1

60.1

86.6

111

128

138

143

147

149

153

155

157

158

160

165

0.00

2.92

5.86

6.45

7.03

7.62

8.21

9.23

10.8

13.6

18.5

28.1

47.2

85.0

147

215

234

182

113

64.9

38.5

24.6

17.2

9.63

7.19

4.50

3.39

1.64

0.15

0.00

0.70

2.68

3.24

3.84

4.50

5.22

6.00

6.91

8.04

9.55

11.8

15.5

22.1

34.0

52.9

76.2

96.8

110

115

118

121

122

123

123

122

121

117

85.8

0.00

0.76

2.91

3.49

4.13

4.81

5.55

6.36

7.29

8.43

9.95

12.2

15.8

22.3

33.9

52.1

74.5

93.8

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.01

0.01

0.01

0.01

0.01

0.02

0.02

0.03

0.04

0.07

0.12

0.23

0.38

0.58

0.85

1.14

2.01

2.81

4.20

5.23

11.0

56.9

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.01

0.01

0.01

0.01

0.02

0.02

0.03

0.04

0.05

0.08

0.16

0.00

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.02

0.02

0.04

0.05

0.06

0.07

0.08

0.08

0.09

0.10

0.11

0.11

0.12

0.08

0.00

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.02

0.03

0.04

________________ .L I I I I

') All nun•rical values a=e presented at elevation with peak pocr

1-28
#B20C I Indiiduma teristics of Refabricated Fuel Rods -. I(Fresh Fu4 l Cladding) under IGR Tests, iI

Table 1-2.6. Temperature Variation, Fission Gas Release and ZrO2 Thickness Vs. Time for Fuel

Rod #B20C Calculated by FRAP-T6 and SCANAIR Codes

Fuel centerline Fuel surface - Clad outer

Time~s) temperature') temperature') temperature')

(s) (ý) F (K) (K)

FRAP-T6 I SCANAj FRA-T6 SCANAIR FRAP-T6 SCANAIR

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

306

341

351

361

372

384

397

412

430

454

489

546

644

817

1087

1422

1724

1922

2030

2084

2107

2112

2091

2067

2033

2010

1922

1498

293'

305

340

350

360

371

383

395

410

427

450

483

536

626

783

1023

1317

1579

293

305

336

345

354

364

375

387

400

416

438

469

518

601

738

932

1135

1288

1379

1420

1532

1647

1691

1737

1754

1768

1773

1769

1449

293 -

305

338

346

356

366

377

389

402

419

441-

473

524

610

755

962

1182

1349

293

296

312

317

323

330

337

345

355

365

377

392

413

445

500

595

744

927

1076

1167

1270

1299

1330

1406

1457

1514

1540

1591

1351

293

297

313

319

325

332

340

349

358

369

382

399

422

460

524

635

800

991

"All numerical values arc presented at elevation %ith peak power

1-29
#B20C 'Individiul Chaiz"0d fRefabricated Fuel Rods

'i(Fresh Fuel, Freish.jgTijln'g) under IGR Tests.:

Table 1-2.7. Mechanical Characteristics of Fuel Rod #B20C Vs. Time Calculated by FRAP-T6 and

SCANAIR Codes

Clad outer Fuel hoop Fuel - clad gap Clad hoop Clad hoop Internal gas Time temperature') strain') width') straint) stress') pressure

(S) (K) (%) (mm) 0(0 (MPa) (MPa)

____ ,r6CAA Fr.T61SCANAI FRA, T6 S-Rj Fl E -T6JS F ,,-CANAlR T6JSCANAM

0.0

1.0

2.0

2.2

2.4

2.6

2.8

3.0

3.2

3.4

3.6

3.8

4.0

4.2

4.4

4.6

4.8

5.0

5.2

5.4

5.6

5.8

6.0

6.5

7.0

7.5

8.0

10.0

30.0

293

296

312

317

323

330

337

345

355

365

377

392

413

445

500

595

744

927

1076

1167

1270

1299

1330

1406

1457

1514

1540

1591

1351

293

297

313

319

325

332

340

349

358

369

382

399

422

460

524

635

800

991

0.00

0.01

0.04

0.05

0.06

0.07

0.08

0.09

0.11

0.13

0.15

0.19

0.24

0.34

0.51

0.80

1.19

1.56

1.80

1.91

1.97

2.01

2.02

2.02

2.00

1.97

1.95

1.86

1.32

0.00

0.01

0.03

0.04

0.05

0.05

0.06

0.07

0.08

0.10

0.11

0.14

0.18

0.26

0.A

0.66

1.00

1.32

0.10

0.10

0.09

0.09

0.09

0.09

0.09

0.09

0.09

0.09

0.09

0.09

0.09

0.09

0.08

0.07

0.06

0.05

0.05

0.05

0.24

1.86

1.86

1.86

1.86

1.86

1.86

1.86

1.88

0.10

0.10

0.09

0.09

0.09

0.09

0.09

0.09

0.09

0.09

0.09

0.09

0.09

0.09

0.09

0.08

0.07

0.07

0.01

0.01

0.02

0.03

0.03

0.03

0.04

0.05

0.05

0.06

0.07

0.08

0.09

0.11

0.15

0.22

0.32

0.45

0.55

0.62

5.12

45.4

45.4

45.5

45.5

45.6

45.6

45.6

45.4

0.01

0.01

0.03

0.03

0.03

0.04

0.05

0.05

0.06

0.07

0.08

0.09

0.11

0.14

0.19

0.28

0.40

0.55

10.5

10.5

10.7

10.7

10.8

10.8

10.9

10.9

11.0

11.0

11.1

11.2.

11.4

11.6

11.8

12.1

12.3

12.5

12.6

12.7

13.8

0.00

0.00

0.00

0.00

0.00

0.00

0.00

0.00

10.4

10.5

10.7

10.7

10.8

10.8

10.9

10.9

11.0

11.0

11.1

11.2

11.4

11.6

11.9

12.2

12.4

12.5

2.00

2.01

2.04

2.05

2.06

2.07

2.08

2.09

2.10

2.11

2.12

2.14

2.16

2.20

2.25

2.30

2.34

2.37

2.39

2.40

2.37

0.10

0.10

0.10

0.10

0.10

0.10

0.10

0.10

2.00

2.01

2.04

2.05

2.06

2.07

2.08

2.08

2.09

2.11

2.12

2.14

2.16

2.20

2.24

2.28

2.31

2.33

1) All numerical values are presented at elevation with peak pomer

1-30
#B20C I individual ,'a teristics of Refabricated Fuel Rods-,'

I (Fresh F0r•-esh Cladding) under IGR Tesits

Table 1-2.8. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6 Code

for Fuel Rod #B20C

Axial interval Energy deposition at infinite time Fuel enthalpy

from-to at time (t-6.50 s)

(mm)-(mm) caLig fuel J/g fuel per-unit cal/g fuel J/g fuel per-unit

24.0-38.2 169 709 1.00 123 516 1.00

38.2-52.4 167 700 0.99 122 509 0.99

52.4-66.6 165 690 0.97 120 502 0.97

66.6- 80.8 163 682 0.96 119 497 0.96

80.8-95.0 162 677 0.96 .118 493 0.96

95.0- 109.2 160 670 0.95 116 488 0.95

109.2 - 123.4 160 669 0.94 116 487 0.94

123.4 - 137.6 159 666 0.94 116 485 0.94

137.6 - 151.8 161 673 0.95 117 490 0.95

151.8- 166.0 162 680 0.96 118 495 0.96

180

" 160

• 140

.12

100

80

106- 

40

20

0

20 40 60 80 100 120

Axial coordinate (mm)

140 160 180

Fig. 1-2.5. Axial Distribution of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6 Code

for Fuel Rod #B20C

1-31
#B20C Individual Cha`rasdfýcsofRefabricated Fuel Rods

(Fresh Fuel,-Frest,•-l1-ding) under IGR Tests

1.2

V)

0

1.0

0.8 --

0.6 +

2

IV

0.4 -

0.2

1 3 4

Radial fuel coordinate (mm)

14

12

10

U

Co

(U

U

C

w

8

6

4

2

0

.0

:0

0-

0I 0-0- -..O.- 3.0 .0ss

I..-0- 6.5 s

0o

•0

r"

0 -i

1.0 1.5 2.0 2.5 3.0 3.5 4.0

Radial fuel coordinate (mm)

Fig. 1-2.6. Radial Distributions of Energy Deposition and Fuel Enthalpy Calculated by FRAP-T6 Code

for Fuel Rod #B20C

1-32
r! e AMiP

Nb.::_•.:.i-.• diaddf-f.tg,:,

J-1
Table J.1. Characteristics of unirradiated Zr-l%Nb cladding used to manufacture ring specimens

Characteristic Unit Value

1. Composition

Zr % by weight 98.505 - 98.705

Nb % by weight 0.9-1.1

0 % by weight 0.11

N % by weight 0.0061

C % by weight 0.02

Si % by weight 0.02

Al % by weight 0.008

Mo % by weight 0.005

Ni % by weight 0.05

Fe % by weight 0.05

Other elements % by weight 0.126

2. Treatment - annealing at 580 °C, 3 hours

3. Outer diameter mm 9.14+0-o9

4. Inner diameter mm 7.72+. oo&

J-2
Table J.2. Results of ring tensile tests on unirradiated Zr-1%Nb cladding (strain rate 0.002 11s)

Temperature Ultimate Yield Total Uniform

strength stress elongation elongation

(K) (MPa) (MPa) (%) (%)

349 294 31.5 8.3

293

345 297 30.3 7.9

267 235 35.8 7.7

423

268 233 32.4 8.2

219 189 31.3 8.7

523

228 195 30.8 8.4

173 149 31.9 7.7

653 178 156 34.6 8.2

180 153 32.2 7.8

150 140 38.5 4.5

753

154 134 38.7 6.4

139 122 41.1 6.1

793 132 122 42.0 6.2

140 123 42.7 , 5.8

873 84 79 63.2 7.3

66 62 76.6 5.9

923

68 61 71.9 5.3

43 39 79.3 4.4

1023 43 41 76.4 3.9

43 39 80.6 4.9

34 32 90 3.3

1073 29 27 71.5 4.5

35 32 88.9 4.1

19 18 54 3.6

1123 15 13 * *

21 20 79.3 4.9

1223 14 12 61.6 4

* not measured

J-3
Table J.3. Results of ring tensile tests on unirradiated Zr-1 %Nb cladding vs. strain rate

Strain Temperature Ultimate Yield Total Uniform

rate strength stress elongation elongation

(l/s) (K) (MPa) (MPa) (%) (%)

378 341 25.8 *

373 331 25.5 *

293 378 336 27.0 *

377 342 26.2 *

380 339 28.0 *

172 159 26.3

623 177 163 30.7 *

0.002 873 84 79 63.2 7.3

66 62 76.6 5.9 923

68 61 71.9 5.3

43 39 79.3 4.4 1023

43 41 76.4 3.9

1073 35 32 88.9 4.1

21 20 79.3 4.9 1123

19 18 54.0 3.6

0.02 1223 13 11 57.4 *

873 129 119 45.2 6.7

S110 97 55.7 7.2

106 92 55.4 6.5

1023 81 70 67 7.4 0.1

1073 66 63 82.3 3.3

49 45 70.3 3.6 1123

42 39 55.9 5.3

1223 16.5 14.3 33.8 5.3

401 362 19.6 *

409 356 21.4 * 0.2 293

409 372 24.0 *

403 362 20.9 *

422 395 18.7 *

293 416 384 19.4 *

0.5 418 378 19.9 *

198 182 28.3 *

623 193 176 28.9 *

• not measured

J-4
Strain

rate

Strain

rate .

0.21/s,

Fig. J.1. Appearance of unirradiated ring specimens after mechanical tests vs. strain rate (T=293 K)

Fig. J.2. Appearance of unirradiated ring specimens after mechanical tests vs. strain rate (T=623 K)

J-5
Table J.4. Characteristics of commercial fuel rod and irradiated cladding fragment used to manufacture ring specimens

Characteristic Unit Value

Characteristics of commercial VVER fuel rod

Power plant Unit #5 of NV NPP

Fuel assembly number 4108

Fuel rod number - 165

Fuel burnup MWd/kgU 48

Fuel rod length mm 3832

Characteristics of cladding

Cladding fragment coordinates mm 1542- 2062

Outer diameter mm 9.066

Cladding thickness mm 0.69±0.015

ZrO2 thickness on outside of cladding pm 3 -5

ZrO2 thickness on inner side of cladding pm <1

Hydride orientation coefficient 0.35 -0.42

Hydrogen concentration % by weight (4.9 - 5.8). 10.3

Position 1

-1 t.

'I

J ~'

'-1

a

Position 2

Fig. J.3. Microstructure of irradiated Zr-1%Nb cladding

J-6
60

8-

50

40

30

burnup.grf

1500 1600 1700 1800

Axial coordinate (mm)

a)

1900 2000 2100

91 rprofil.grf

Z9.10

, 9.05

9.00

1500 1600 1700 1800

Axial coordinate (mm)

b)

1900 2000 2100

signalgrf I

0

0

0

-1

-2

1500 1600 1700 1800

Axial coordinate (mm)

c)

1900 2000 2100

Fig. J.4. a) Axial burnup distribution, b) results of profilometry and c) eddy-current examination for

irradiated 1%Nb cladding

J-7
Table J.5. Results of plain ring tensile tests on irradiated Zr-l%Nb cladding (strain rate 0.002 1s)

Temperature Ultimate, Yield Total Uniform

strength stress elongation elongation

(K) (MPa) (MPa) (%) (%)

542 470 23.9 6.2

541 484 10.2 5.1

559 490 16.3 4.9

540 469 13 4.5

555 479 17.3 4.9

548 481 11.1 5.2

512 437 18.5 4.7

423 523 457 11.3 4

521 435 14.6 4.6

392 324 16.3 6.7

434 365 16.9 5.5

455 395 18.3 4.4

388 341 21 5.1

403 356 17.3 3.7

653 391 336 18.1 4

362 314 18 4.1

300 251 16.8 4.7

753 225 191 33.5 5.3

341 304 14.9 4.1

171 138 *

144 133 * *

168 142 * *

189 167 37 4.4

90 81 *

863 87 79 * *

63 56 * *

923 65 58 * *

74 67 75.3 5.8

973 52 48 * *

42 37 94.5 5.1

1023 40 34 * *

37 32 * *

1073 33 30 80 4.1

16 15 77.6 4.8

13 10 *

1123 17 13 * *

14 11 *

15 14 70 4

14 9 *. *

1223 1

20 11 * *

• not measured

J-8
Table J.6. Results of plain ring tensile tests on irradiated Zr-1%Nb cladding vs. strain rate

Strain Temperature Ultimate Yield Total Uniform

rate strength stress elongation elongation

(1/s) (K) (MPa) (MPa) (%) (%)

293 550 463 16.9 *

653 362 314 18.0 *

753 317 274 12.4 *

0.002 793 161 137 40.0 *

923 74 67 75.3 5.8

1023 42 37 94.5 5.1

1073 33 30 80.0 4.1

185 160 33.5 *

793 200 178 30.4 *

227 177 33.9 *

923 131 112 44 6.9

0.1

1023 85 78 67.6 8.1

1073" 67 61 70.0 5.9

1223 21 14 25.4 12.4

1323 20 13 70.1 21

575 528 12.0 *

293 591 533 13.9 *

607 535 13.9 *

414 380 17.4 *

0.5 653 407 352 18.9 *

389 350 16.1 *

361 323 15.9 *

753 357 304 15.6 *

354 306 16.2 *

* not measured

J-9
/ 2

Fig. J.5.. Appearance of Irradiated ring specimens after mechanical tests (strain rate - 0.002 11s)

J-10
K-1
Table K.I. Characteristics of unirradiated Zr-l%Nb cladding used to manufacture tube specimens

Characteristic Unit Value

1. Composition

Zr % by weight 98.505 - 98.705

Nb % by weight 0.9-1.1

0 % by weight 0.11

N % by weight 0.0061

C % by weight 0.02

Si % by weight 0.02

A] % by weight 0.008

Mo % by weight 0.005

Ni % by weight 0.05

Fe % by weight 0.05

Other elements % by weight 0.126

2. Treatment annealing at 580 C, 3 hours

3. Outer diameter mm 9.14+.0009

4. Inner diameter mm •7.7+0

K-2
Test #29

0.01

MPa s

Fig. K.I. Appearance of pressurized unirradiated tube specimens after test (temperature 973 K)

Test #30

0.011

MPals

Fig. K.2. Appearance of pressurized unirradiated tube specimens after test (temperature 1023 K)

K-3
Test #16

0.0035

MPa/s

0.01

MPa/s

0.0153 1

MPa/s

. Test #14

7 77 77, ilN* I I . - -

Test # 1

~1iiI IRELTest #2

:0.082

MPa/s

Test #31

.. 0.9

"MPa/s

Fig. K.3. Appearance of pressurized unirradiated tube specimens after tests vs pressure increase rate

(temperature 1073 K)

K-4
Test # 18

0.01

MPa/s

Fig. K.4. Appearance of pressurized unirradiated tube specimens after test (temperature 1126 K)

Test #32

0.01 -

Test # 13

Mea/s___.. ._____

Test #3

0.024 w MPa/s ________

Test #4

o0083 =

MPa/s

Test #33

1.09 

:

MPaS/

Fig.K.5: Asi

Fig. K.5. Appearance of pressurized unirradiated tube specimens after tests vs pressure increase rate

(temperature 1173 K)

K-5
.. Test #12

0.009

:MPa/s

Test #5

0.087

MPa/s

Test #34

MPa/s

Test #6

M A

a.1 MPa/s"[

Fig. K.6. Appearance of pressurized unirradiated tube specimens after tests vs pressure Increase rate

(temperature 1273 K)

. K-6
Fig. K.7. Appearance of pressurized unirradiated tube specimens after tests vs pressure Increase rate

(temperature 1373 K)

K-7
Test #17

0.01

MPa/s

Test #10

0.502*-

MPa/sl

Test #36

MPa/s

Fig. K.8. Appearance of pressurized unirradiated tube specimens after tests vs pressure Increase rate

(temperature 1473 K)

K-8
T-973 K (Test #29) .T=1023 K(Test #30)

T=1073 K (Test #14) . - T=1126 K(Test #18),:

T-i 173 K (Test #32) T=1273 K (Test #12)

,.: -T=1373 K (Test #11) -:T=1473 K (TeSt#17): 0 __

Fig. K.9. Cross-section profiles of burst region vs temperature (unirradiated cladding, 0.01MPa/s)

K-9
Test #16 (0.0035 MPa/s) Test #14 (0.01 MPa/s)

Test #1 (0.0153'MPa/s) Test #2 (0.082 MPa/s)

Test #31 (0.9 MPa/s):i,.,

Fig. K.10. Cross-section profiles of burst region vs pressure increase rate

(unirradiated cladding, T=1073 K)

K-10
•s) J. Test #33 (1.09 MPa/s)

Fig. K.11. Cross-section profiles of burst region vs pressure increase rate

(unirradiated cladding, T=1173 K)

K-1 I
.: .Test #12 (0.009 MPa/s) . Test #5 (0.087 MPa/s)

-Test #34 (.1 MP s) Test #6 (1.1 MPa/s)

Fig. K.12. Cross-section profiles of burst region vs pressure Increase rate

(unirradiated cladding, T=1273 K)

K-12
* Test #11 (0.01 MPa/s) * - Test #7 (0.087 MPa/s)

: Test #8 (0.458 MPa/s) Test #35 (0.91 MPaes)

Fig. K.13. Cross-section profiles of burst region vs pressure increase rate

(unirradiated cladding, T-1373 K)

K-13
Test #17.(0.01 MPa"s) Test #10 (0.502 MPa/s)

Test #36 (1.1 MPaS/s)

Fig. K.14. Cross-section profiles of burst region vs pressure increase rate

(unirradiated cladding, T=1473 K)

K-14
Table K.2. Burst parameters of unirradiated tube specimens vs temperature and pressure increase

rate

Test Tempe- Pressure Burst Average Axial Circumfe- Wall

number rature increase pressure circumfe- radius of rential thickness

(K) rate (MPa) rential curvature radius of at burst

(MPa/s) strain (mm) curvature (mm)

(%) (Mm)

29 973 0.01 11.27 84.1 49.6 7.77 0.38

30 1023 0.011 8.49 92.3 59.3 8.12 0.36

16 0.0035 4.48 106.5 39.9 8.72 0.16

14 0.01 5.75 49.2 149 6.30 0.27

1 1073 0.0153 6.03 40.2 214 5.92 0.29

2 0.082 6.35 51.4 262 6.39 0.22

31 0.9 12.35 48.1 329 6.26 0.25

18 1126 0.01 3.13 49.2 141 6.30 0.18

32 0.01 1.60 36.7 70.0 5.77 0.22

13 0.011 1.65 * 63 * *

3 1173 0.024 1.96 41.5 412 5.98 0.20

4 0.083 2.25 45.1 260 6.13 0.25

33 1.09 3.08 40.9 206 5.95 0.30

12 0.009 1.42 7.8 62 4.55 0.26

5 0.087 1.59 8.4 112 4.58 0.32

1273

34 1.1 2.34 58.9 489 6.71 0.19

6 1.1 2.76 46.8 * 6.20 0.24

I 1 0.01 1.19 13.0 10.6 4.77 0.30

7 0.087 1.59 50.9 480 6.37 0.24

1373

8 0.458 1.81 53.8 389 6.50 0.26

35 0.91 1.89 62.8 * * 0.20

17 0.01 0.84 68.4 51 7.11 0.25

9 0.088 1.52 * * * * 1473

10 0.502 1.50 24.3 15.4 5.25 0.35

36 1.10 1.71 59.0 304 6.72 0.21

*Not measured

K-15
Table K.3. Characteristics of commercial fuel rod and irradiated cladding fragment used to

manufacture tube specimens

Characteristic Unit Value

1. Characteristics of commercial VVER fuel rod

1.1 Power plant - Unit #5 of NV NPP

1.2 Fuel assembly number 4108

1.3 Fuel rod number 153

1.4 Fuel bumup MWd/kgU 47.5

1.5 Fuel rod length mm 3832.01

2. Characteristics of cladding fragment

2.1 Cladding fragment coordinates mm 712-2477

2.2 Tube specimen length mm 150

2.3 Outer diameter mm 9.08

2.4 Cladding thickness mm 0.69±0.015

2.5 ZrO2 thickness on outside of cladding pm 4-7

2.6 ZrO2 thickness on inner side of cladding pm <1

2.7 Hydride orientation coefficient 0.36- 0.41

2.8 Hydrogen concentration % by weight 0.0051 - 0.0057

Table K.4. Characteristics of Irradiated tube specimens

Test Temperature Cladding Outer diameter Burnup

number fragment

(K) coordinates (mm) (MWd/kgU)

(mm)

19 1373 1871-2021 9.075+o0o01 48.03

20 1173 2023-2173 9.074 ±0-o09 47.22

21 1273 2175-2325 9.080 ±00,o1 47.44

23 1073 2327-2477 9.078 0-60' 47.63

24 1473 1415-1565 9.084±0_012 47.51

26 1273 1719-1869 9.081 '47.15 05 

2177 8 0.004 4

28 1373 712-862 9.78±oo06473 1-1-0:0o747 9 .7 

K-16
Position I

Position 2 

* ... . , . 

;:.?... * ~ 

Fig. K.15. Microstucture of irradiated Zr-I%Nb cladding

K-17
60

E

50

40

30

9.15

600 1100 1600 2100 260(

Axial coordinate (mm)

a)

I4)

C.)

9.10

9.05

9.00

600 1100 1600

Axial coordinate (mm)

2100 2600

b)

0.5

0.

I0.0

I rn~. I

-0.5

-1.0

600 1100 1600

Axial coordinate (mm)

c)

2100 2600

Fig. K.16. Axial burnup distribution a), results of profilometry b) and eddy-current examination c) for Irradiated Zr-I %Nb cladding fragment

K-18
Fig. V-17. Appearance of pressurized irradiated tube specimens after tests vs temperature

(strain rate 0.01MPa/s)

K-19
T-1373 K

Test #19

Test #28

T=1373 K'

Fig. K.17. Appearance of pressurized irradiated tube specimens after tests vs temperature

(strain rate 0.01MPa/s) (Contd.)

Fig. K.18.. Cross-section profiles of burst region vs temperature (irradiated cladding, 0.01 MPa/s)

K-20
Table K.5. Burst parameters of irradiated tube specimens vs temperature and pressure increase rate

Test Tempe- Pressure Burst Average Axial Circumfe- Wall

number rature increase pressure circumfe- radius of rential thickness

(K) rate (MPa) rential curvature radius of at burst

(MPa/s) strain (mm) curvature (mm)

_ _ _ _ _(mm)

43 973 10.49 * * * *

42 1023 6.94 * * * *

23 1073 5.43 57.7 150 6.66 0.21

49 1.76 30.2 7.3 5.50 0.28

1173

20 1.95 28.4 10.4 5.43 0.27

0.01

21 1.93 8.9 21.8 4.60 0.20 1273

26 1.46 8.3 45 4.57 0.25

28 1.27 * * * *

1373

19. 1.11 28.0 272 5.41 0.27

24 1473. 1.24 20.4 28.4 5.09 0.25

45 1073 1.1 7.41 59.3 38.9 6.72 0.30

46 1273 0.91 2.46 * * * *

47 1473 0.90 2.09 * * * " *

*Not measured

K-21

NRC FORM 335 U.S. NUCLEAR REGULATORY COMMISSION I. REPORT NUMBER

(2-) (Assigned by NRC. Add Vol, Supp., Rev,

NRCM o BIBUOGRAPHIC DATA SHEET and Addendum Numbers, If any.)

3201.3202 IUGAHCDTSET

(See I ton on U revens) NUREG/AA-0156

2. TITLE AND SUBTITLE Volume 3

Data Base on the Behavior of High Bumup Fuel Rods with Zr-1 %Nb Cladding and

U02 Fuel (VVER Type) under Reactivity Accident Conditions 3. DATE REPORT PUBUSHED

MOWNT j YEAR

Volume 3 Test and Calculation Results July 1999

4. FIN OR GRANT NUMBER

W6500

5. AUTHOR(S) 6d-.YP."UF-REPOFI

L. Yegorova, G. Abyshov, V. Malofeev, et al. IPSN 99/08-2 NSI RRC KI-2179

A. Bortash, M. Kalugin, et al.

V. Smirnoiv, A. Goryachev, V. Prokhorov, et al. 7. PERIOD COVERED (lneusve Dales)

V. Pakhnitz, A. Vurim

8. PERFORMING ORGANIZATION - NAME AND ADDRESS (VNRC, provide Divisiom Office orReg/o U.S. Nuc/ARegutaboryCommissiotn ad mnaing eddress: ifcowkvo

prvide nnme and maoiing addressj

Russian Research Center "Kurchatov Institute" Moscow 123182 Russia

State Research Centre "Research Institute of Atomic Reactors" Dimitrovgrad Russia

Institute of Atomic Energy of NNC Semipalatinsk Kazakhstan

9. SPONSORING ORGANIZATION - NAME AND ADDRESS (h` NRC type Sarme as above' iffoonradaorpIovide NRCIDiv/sion, Offrceor e~on. U.S. NucleaRegulelry Comminissi

and mailing address.j

Division of Systems Analysis and Regulatory Effectiveness

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, DC 20555-0001

10. SUPPLEMENTARY NOTES

11. ABSTRACT I2oo words or eOs)

The present report contains a data base used for analyzing the behavior of three types of VVER fuel rods (fresh fuel rods;

fuel rods with fresh fuel and irradiated cladding; high burnup fuel rods) which have been tested in the IGR under reactivity accident

conditions. The basic test parameters are as follows: capsule tests with stagnant water or air coolant under ambient conditions;

pressurized fuel rods; fuel burnup: 0 and 48 MWd/kg U; pulse width - about 700 mis.

The presented data base includes the results of reactor tests of 25 fuel rods as well as results of pre- and post-test examinations of

fuel rods, computer simulations of fuel rod behavior under test conditions; in addition, the report presents the results of special

out-of-pile tests carried out to measure mechanical properties of Zr-1%Nb cladding.

The report consists of three volumes, each volume contains the following Information:

Volume 1 :Brief description of the test program, testing and analytical techniques and summary of results;

Volume 2:Description and validation of procedures used to obtain the data base. Summarization of test results as supported by

mechanical properties of Zr-1%Nb cladding;

Volume 3:Data base consisting of: parameters of VVER fuel rods before and after irradiation at the NovoVoronezh Nuclear Power

Plant; parameters of fresh and refabricated fuel rods before and after IGR tests; results of out-of-pile mechanical tests of

non-irradiated and irradiated Zr-1%Nb cladding.

12. KEY WORDS/DESCRIPTORS (Ust words orjplvase that will assist researchers in loating the report.) 13. AVAILABILITY STATEMENT

" ' unlimited

reactiVity initiated accident 14. SECURnYCLASSIFICATON

impulse graphite reactor (Kazakhstan Atomic Energy Agency) 14. pe)

Zirconium -1% Niobium alloy uncassfie

FRAP-T6 & SCANAIR computer codes unclassied

material properties (This Rep)

cladding strain and ballooning unclassified

refabrication of VVER fuel rods 15. NUMBER OF PAGES

post-test examinations

16. PRICE

NRC FORM 335 (2-Mg This form was e;ectronically produced by Elde Federal Faffns. Inc.
Federal Recycling Program