NUREG/IA--0094

STUDSVI K/NS-90/93

International

Agreement Report

Assessment of RELAP5/MOD3

Against Twenty-Five -Post-Dryout

Experiments Performed at the

Royal Institute of Technology

Prepared by

Lars Nilsson

Swedish Nuclear Power Inspectorate

6-61182 Nykoping

Sweden

Office of Nuclear Regulatory' Research

U.S. Nuclear Regulatory Commission

Washington, DC 20555

May 1993

Prepared as part of

The Agreement on Research Participation and Technical Exchange

under the International Thermal-Hydraulic Code Assessment

and Application Program (ICAP)

Published by

U.S. Nuclear Regulatory Commission
NOTICE

This report was prepared under an international cooperative

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the United States Government nor any agency thereof, or any of

their employees, makes any warranty, expressed or implied, or

assumes any legal liability or responsibility for any-third party's

use, or the results of such use, of any information, apparatus proIduct or process disclosed in this report, or represents that its use

by such third party Would not infringe privately owned rights.

Available from

Superintendent of Documents

U.S. Government Printing Office

P.O. Box 37082

Washington, D.C. 20013-7082

and

National Technical Information Service

Springfield, VA 22161
NUREG/IA-0094

STUDS VIK/NS-90/93

International

Agreement Report

Assessment of RELAP5/MOD3

Against Twenty-Five Post-Dryout

Experiments Performed at the

Royal Institute of Technology

Prepared by

Lars Nilsson

Swedish Nuclear Power Inspectorate

6-61182 Nykoping

Sweden

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, DC 20555

May 1993

Prepared as part of

The Agreement on Research Participation and Technical Exchange

undcr the International Thermal-Hydraulic Code Assessment

and Application Program (ICAP)

Published by

U.S. Nuclear Regulatory Commission
NOTICE

This report documents work performed under the sponsorship of the SKI/STUDSVIK

of Sweden. The information in this report has been provided to the USNRC

under the terms of an information exchange agreement between the United States

and Sweden (Technical Exchange and Cooperation Arrangement Between the United

States Nuclear Regulatory Commission and the Swedish Nuclear Power

Inspectorate and Studsvik Enerigiteknik AB of Sweden in the field of reactor

safety research and development, February 1985). Sweden has consented to the

publication of this report as a USNRC document in order that it may receive

the widest possible circulation among the reactor safety community. Neither

the United States Government nor Sweden or any agency thereof, or any of their

employees, makes any warranty, expressed or implied, or assumes any legal

liability of responsibility for any third party's use, or the results of such

use, or any information, apparatus, product or process disclosed in this

report, or represents that its use by such third party would not infringe

privately owned rights.
ZTUDV'rLK NUCLEAR 3TUDVK NULEARSTUDSVIK/NS-90/93

1.990-10-3 2

Lars Nilsson

I CAP

Assessment of RELAP5/MOD3 against twenty-five

post-dryout experiments performed-at the Royal

Institute of Technology

Swedish Nuclear Power Inspectorate

Project No. 90021, Ref .No. 13.3-917/84

Abstract

Assessment of RELAP5/MQD2 has been made against

various experimental data, among others data from

twenty-five post-dryout experiments conducted at

the Royal Institute of Technology (RIT) in Stockholm. As the MOD3 version of RELAP5 has now been

released, incorporating a different method of calculating critical heat flux compared to RELAP5/MOD2,

it seemed justified to make another assessment

against the same RIT-data.

The results show that the axial dryout position is

generally better predicted by the MOD3 than by the

MOD2 version. The prediction is, however, still

nonconservative, i.e. the calculated dryout position

falls in most cases downstream the actual measured

point. While the pre-dryout heat transfer 'seems to

be equal for MOD2 and MOD3, both versions giving

slightly higher wall temperatures than the experiments, there is a considerable difference in the

post-dryout heat transfer. The results of the RIT

data comparison indicate that MOM3 underpredicts

the post-dryout wall temperatures remarkably while

Mod2 gave reasonable agreement. In this respect

RELAP5/MOD3 shows no improvement over RELAP5/140D2.

ISBN 91-7010-142-6

Copyright Studvik AB, Approved by 7

Sweden 1990 L 7i1 L

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STUDVIK NUCLEAR~ STUDSVIK/NS-90 /93

1990-10-12

List of contents

Executive sumrmary

Nomenclature

1 Introduction

2 Facility and test description

2.1 The loop

2.2 Test section

2.3 Experimental program

2.4 Tests selected for the assessment

3 Results of previous RELAP5/MOD2

assessment

3.1 Standard RELAP5/MOD2 simulation

3.2 RELAP5/MOD2 forced CHF simulation

4 The new critical heat flux method

in MOD3

5 input description and geometrical

model

5.1 Geometrical model

5.2 Changes from M~OD2 to MOD3 input

6 Performance of the calculations

and computational efficiency

7 Results and data comparison

7.1 Critical heat flux prediction

7.2 Post-dryout heat transfer

7.3 Nodalization studies

7.4 Calculations on experiments with nonuniform axial heat flux distributions

8 Conclusions

Page

3.

4

5

5

7

9

10

13

14

14

15

18

19

20

24

26

27

28

30

31

32

References

List of tables

List of figures

Appendix A

Appendix B

Appendix C

Appendix D

Input to RELAP5/M0D3

CPU times for the Sun computer

Tables of measured and calculated

wall temperatures

Plots of measured and calculated

wall temperatures for the RIT

cases in which dryout occurred

V A:LN/RAPP

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Executive suzmmary

Assessment of.RELAP5/MOD3 has been made against

twenty-five post-dryout experiments conducted at

the Royal Institute of Technology (RIT) in Stockholm. A similar assessment has earlier been perf ormed of RELAP5/MOD2. As the MOM3 version of RELAPS

has now been released, incorporating another method

of calculating critical heat flux (CHF), it seemed

justified to make another assessment against the

same RIT-data.

in the experiments wall temperatures were measured

on an electrically heated, 7 m long tube with an

inner diameter of 14.9 mm. The tube was cooled by

upwards flow of water with mass fluxes from 500 to

2000 kg/m2s. The cases selected for this assessment

covered pressures ranging from 3 to 14 M'Pa, heat

fluxes from 400 to 1060 kW/m2 and inlet subcoolings

from 8.5 to 12 K.

The RELAP5 model used for the simulations comprised

47 axial fluid cells. A fine nodalization was employed for the upper part of the test section where

post-dryout conditions took place.Time dependent

pressure, temperature and flow boundary conditions

were imposed to simulate the fluid entering the

test section. The region downstream of the test

section was modelled by a time dependent pressure

boundary condition. The axial heat flux distribution was uniform. An insulated boundary condition

was imposed upon the outside edge of the tube wall

while the inner edge received its boundary condition - a heat transfer coefficient and a temperature

sink - from the RELAP5 heat transfer package. Once

the RELAP5 simulations reached steady state the

axial temperature distribution along the tube was

compared to experimental values.

The new method for calculating critical heat flux

in RELAP5/MOD3 uses a four-dimensional table with

the heat flux as a function pressure, mass flux

and steam quality based upon "Groenevelds CHF Lookup Table". This procedure replaces the Biasi correlation in RELAP5IIIOD2. After interpolation has

been done in the table eight multipliers are imposed

on the CUF value to account for effects of diameter,

bundle geometry, heat flux distribution etc. All

of the analyzed RIT data were within the range of

the MOM3 tables.

The results of the RELAP5/MOD3 assessment show

some improvement in the CHF prediction compared to

MOD2. The axial dryout position is generally better

predicted by the MOD3 than by the MOD2 version.

The prediction is, however, still non-conservative,

i.e. the calculated dryout position falls in most

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1990-10-12

cases downstream the actual measured point. Especially at the lowermost pressure, 3 MPa, the new

dryout calculational method in NOD3 showed no improvement over the MOD2 method. In both cases overpredictions of the dryout heat flux by as much as a factor

of three could be obtained.

While the pre-dryout heat transfer seem to be equal

f or MQD2 and MOD3, both versions giving slightly

higher wall temperatures than the experiments,

there is a considerable difference in the post-dry-

.out heat transfer. In order to make a relevant

comparison the point of onset of dryout should be

correctly predicted. In the M'1D2 assessment this

was achieved through a code modification forcing

the measured dryout position into the calculations.

In the present case with MOM3 one of the CHF multipliers, was used to adjust the calculated CHF to

agree with the observed one. With this condition

RELAP5/MOD2 gave a satisfactory agreement between

calculated and measured post-dryout wall temperatures, in general within 10 K. The results from

RELAP5/MOD3, however, show a considerable underprediction of the temperatures. There has obviously

been an exchange of the models in the subroutine

PSTDNB which leads to larger post-dryout heat transfer coefficients in MOD3 than in MOD2. In this

respect RELAP5/MO2D3 shows no improvement over

RELAP5/MQD2. The differences in the coding seen in

the source code list is not explained here as the

model description of MOM3 was not released at this

moment. The reasons for the changes are also unclear.

Nodalization studies with longer test section cells

show that increasing the length from 0.10 to 0.5 m

did not remarkably impair the temperature predictions.

The larger cell length, which is typical in nuclear

reactor simulations, lead of course to a less good

resolution for the calculated axial dryout point

and for regions with steep temperature gradients.

The computational efficiency seem to have been

improved from !40D2 to M'1D3. One reason is that the

CHF calculation is now less time consuming as the

CHF value from !40D3 is directly compared with the

actual surface heat flux, instead of as in MOM0D

use a iteration scheme for the wall temperatures.

However there still remains an inconsistency in

the steady state convergence algorithm, which if

improved could further reduce the computation

time.

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3

Nomienclature.

Symbol Definition Units

G

L

p

q I II

q/A

R

T

U

x

z

A

Mass flux

Length

Pressure

Volumetric heat generation

Heat flux

Radius

Temperature

Voltage

Steam quality

Axial coordinate

Thermal conductivity

Electric resistivity

kg/l(mr ,s)

m

Pa.

W/m 2

K

V

W/ (mn,K)

Subscript

c

in

calculated

measured

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1990-10-12

1 Introduction

The International Thermal-Hydraulic Code Assessment

and Applications Program (ICAP) is beeing conducted

by several countries and is coordinated by the US

NRC. The goal of ICAP is to make quantitative statements regarding the accuracy of the current stateof-the-art thermal-hydraulic computer programs

developed under the auspices of the US NRC.

Sweden's contribution to ICAP relate both to

TRAC-PWR and to RELAP5. The assessment calculations

are being performed by Studsvik AB for the Swedish

Nuclear Power Inspectorate. The currrent assessment

matrix is shown in Table 1.

Table I

ICAP Assessment Matrix - Sweden

Code Facility Type Description

Sep. effect Integral

RELAP5 Marviken22 X Subcooled critical flow.

RELAP5 Marvikenll X Critical flow, level swell

RELAP5 FIX-11 X Recirculation line (10%) braek

RELAP5 FIX-II IX Recirculation line (31%) braek

RELAPS FIX-11 x Recirculation line (200%) braek

RELAP5 LoOFT x Cold leg braek (4"), pumps off

RELAPS LOFT x Cold leg break (4"1), pumps on

PELAPS FRIGG X Subcooled void distribution

RELAP5 FRIGG x Critical heat flux

RELAP5 RIT. x Post dryout heat transfer

TRAC/PF1 Ringhals x Loss of load

TRAC/PF1 Ringhals x Feed water line isolation

TRAC/PF1 Ringhals x Steam line isolation

All of the RELAP5 assessments were made with the

MOD2-version. The simulations of 25 selected RIT

post dryout experiments were thus made with RELAPS!

MOD2, cycle 36.02. This assessment was published

in ref. 1.

As the 140D3 version of RELAP5 has an entirely

different method for calculatating critical heat

flux (CHF) it was considered of importance to make

another assessment against the RIT-data. The new

CHF method was claimed to be superior to the one

in MOD2, which was based on Biasi' s correlation.

This work comprises recalculation of the same twentyfive post-dryout experiments, which were employed

in the RELAP5/MOD2 assessment, now with RELAP5/MOD3.

A: LNIRAPP
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2 Facility and test description

The post-dryout experiments analysed in the present

report were obtained at the department of Nuclear

Reactor Engineering at the Royal Institute of Technology in Stockholm. The experimental studies included the measurements of 510 post-dryout wall

temperature distributions for 7 meter long uniformly

heated round ducts as well as 999-temperature distributions for axially non-uniformly heated ducts

of the same length. The latter measurements include

six axial heat flux distributions. The results for

uniform heat flux were reported by Becker et al

(2), and another report (3) concerning the non-uniform axial heat flux-measurements is now in progress.

The investigations covered the pressure range between

10 and 205 bar. The 25 post-dryout experiments

used in the present assessment are all with axially

uniform heat flux and are selected from ref. 2.

The-description of the experimental facility, which

is given in paragraphs 2.1 and 2.2, is reproduced

from ref. 2.

2.1 The loop

The loop employed for the post-CHF experiments was

designed for an operating pressure of 250 bar. All

parts of the loop in contact with water were made

from stainless steel. A simplified flow diagram

for the loop is shown i Figure 1. Test tections

with heated lengths up to 7 300 mm can be accommodated. Power is supplied from a direct current.

generator. The maximum available current is 6 000

amps and voltages ranging from 0 to 140 volts can

be supplied.

Figure 1

Test loop FEED WA~TR PUMP

flow diagram z

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1990-10-12

Before entering the test section the water passes

a 150-kW preheater and a filter. The preheater is

used for adjusting the inlet water temperature.

After the test section the steam-water then enters

a circulation.puxnp, which has a pressure head of

100 meters of water. The major portion of this

pressure head is used in the duct system between

the pump and the test section inlet, thus providing

sufficient throttling in order to secure stable

operation of the loop.

The flowmeter system consists of four 1 000 mm

long ducts of 3.80, 6.29, and 13.2 mm inner diameter. The flow rate measurements were based on

measuring the pressure drop over one of these

ducts with a Barton cell. The accuracy of this

flowmeter system is said to be better than 1 per

cent over the whole range of application.

The static pressure of the loop was measured with

Barton cells connected to pressure taps, which

were located just below and above the test section.

The accuracy of the pressure measurements is 0.1

per cent.

The water temperature was measured before the f lowmeter, before the test section and after the test

section. This was accomplished by means of thermocouples mounted in wells 100 mm deep and 3 mm inner

diameter. The accuracy of the fluid temperature

measurement is 0.5 K.

The power input was obtained by measuring the current through and the voltage over the test section.

The voltage was measured with a precision voltmeter

of 0.25 per cent rated accuracy, and the current

was obtained by measuring the voltage over a calibrated shunt. For the latter measurements a millivoltmeter with a rated accuracy of 0.25 per cent

was used.

in order to check the accuracy of the instrumentation, heat balances for single-phase flow, relating

the electric heat input to the enthalpy increase

of the water were taken every day before starting

the ordinary measurements. The error of the heat

balances was generally less than 1 per cent. If

larger errors were encountered, the instrumentation

was checked and new heat balances were taken before

carrying out the experimental program.

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2.2 Test sections

Three electrically heated round tubes with the

following dimensions were employed.

Test Heated Inner Outer

section length diameter diameter

1 7 000 mm 14.9 mm 20.8 mm

2 7 000 mm 10.0 mm 14.0 mm

3 7 100 mm 24.69 mm 31.7 mm

Test sections 1 and 2 were made from Nimonic and

test section 3 from stainless steel.

The twenty-five experiments chosen for the RELAP 5

assessment were all obtained with test section No. 1.

in order to make it possible to mount the thermocouples on the outer wall of the test sections, a

0.1 mm thick layer of ZrO2 was sprayed on the

outer walls. Fifty-five Chromel-Aluinel thermocouples were placed along the heated length of test

section 1 and 2 in accordance with the axial positions given in Figure 2.

Two copper rings were silver soldered to the test

sections. The distance between these rings are

referred to as the heated length. Finally, a 10 cm

thick layer of stone wool insulation was mounted

around the test section, keeping the heat losses

at a low level, which was verified by means of the

earlier mentioned one-phase flow heat balances.

The outer wall thermocouples were according to

Ref. 2 calibrated by means of adiabatic single

phase flow experiments at 100, 200 and 300 C. The

majority of the thermocouples indicated temperature

dependent correction terms less than 1.5 C. The

maximum correction term , which was observed at

300 C, was 3.6 C.
. STUDSVIK NUCLEAR STUDSIK NULEAI ~STUDSVIK/NS-90/ 938 8

1990-10-12

preessurel~&

*=6.90 6.92

6.8o

6.706.o

6.50 6.6o

6.30 6.20

6.10 6o

5.:90 5.80

5 *70 5.60

55.45

5.30 5.40

5.10 52

4.90 5.00

4.70 *480

4.70 4.6o

4.50 4.40

4.10O 4.00

3.90 3.8o -

3.50 3.60

3.30 3.,40 .

3.10 3.20-

3.10 *3 00

2.*75

2.50-

2.25

2.00-

1 *75

1.50

1.25

1.00

copper ring

thermocoup1i

T55 T52+

-~T51 '"50

T49 T4

T47

- T45 ,T44 T43

- ~T41 "4

T40

~38 -T37 3

356

~34 - T33 T32

---- -- - 31

- T29 -- T28

27 T26

T25 72

- T~21

T20

- - T17 T1 6

13

enumber

9

N

0

0A

6o

ho 7T12

710

-~ 9

S 77

0.50

-0.05 - -73.

pressure tap

copper ring

Figure 2

Location of thermocouples in test section 1 and 2

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1990-10-12

All of the data were recorded by a 100 channel

Schlumrberger data recorder, punched on paper tape

and evaluated by an IBM~-360/60 computer.

The inner wall temperatures were-obtained from the

outer wall temperatures by stepwise integration of

the following equation:

a 2T 18 T q U

a2 R aR A (T) pL 2 AT

This calculation involved the division of the tube

into 20.concentric tubes, and demanded information

about the temperature-dependent electrical resistivity and thermal conductivity of the test sections'

materials. With regard to test sections 1 and 2,

the manufacturer's curve for Nimonic 75 was used

for the thermal conductivity, while the electrical

resistivity was measured in a temperature regulated

oven. The thermal properties are given in Table 2.

Table 2

Thermal properties of test section wall material

Temp Thermal Electric

conductivity resistivity

C W/(mC) Ohm MM 2 /M

100 14.0 1.118

200 15.9 1.130

300 17.6 1.142

400 19.0 1.154

500 21.1 1.160

600 22.4 1.146

700 24.2 1.139

800 26.0 1.138

2.3 Experimental program

in all, 334 runs were carried out with test section

1 in the following ranges of variables:

Heated length

Inner diameter

Outer diameter

Inlet subcooling

Pressure

Mass velocity

*Heat flux

Post-dryout steam quality

7.000 m

14.9 mm

20. 8 mm,

10 + 3 C

30, 50, 70, 100, 120,

140, 160, 180 and 200 bar

500, 1000, 1500, 2000,

2500 and 3000 kgl(m 2 ,s)

10 - 125 W/CM2

0.03 - 1.60

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1990-10-12

copper ring

pressure tap the rmocouple

- 6 . 9 0 0_ _ _.8 _ _ _ 3 _ T 5 2

6.50 66 T1 '5

6.*30 6.20__ T47__ T46

6.*10 6.00 - T45 ,T44 T43

5.05.80 - T1 "42

5.70 5.60 -------- 39 -- T4

5.50 5.40T3 *_38

5.30 5.0T36____

5.10

4.90 4.o-----.3 32

4.70 4.60 T9 3

4.50 - - -T2

4.30 4.o- -T7 26

4.o4.20 Ti:2

3.703.80T20

3 *30 3.4 - - 17 -1

3:1 10T13,2 

number

ri

A

V

A 2.75 - -~T12

2 * 75

2.50

2.*25

2.*00

1.75

10.50

1.00 ---

.-. T7

0.75-. .T

0.50 -

0.25 - --- w12

0.05 - A:-T

pressure tap

copper ring

Figure 2

Location of thermocouples in test section 1 and 2

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1990-10-12

All of the data were recorded by a 100 channel

Schiuniberger data recorder, punched on paper tape

and evaluated by an IBM-360/60 computer.

The inner wall temperatures were obt~ained from the

outer wall temperatures by stepwise integration of

the following eguation:

82 T +1ýT ~ qI U 2 1

BR ~ a ~ 2 (T)= P2 X (T)

This calculation involved the division of the tube

into 20 concentric tubes, and demanded information

about the temperature-dependent electrical resistivity and thermal conductivity of the test sections'

materials. With regard to test sections 1 and 2,

the manufacturer's curve for Nimonic 75 was used

for the thermal-conductivity, while the electrical

resistivity was measured in a temperature regulated

oven. The thermal properties are given in Table 2.

Table 2

Thermal properties of test section wall material

Temp Thermal Electric

conductivity resistivity

C W/(m,C) ohm MM 2 /m

100 14.0 1.118

200 15.9 1.130

300 17.6 1.142

400 19.0 1.154

500 21.1 1.160

600 22.4 1.146

700 24.2 1.139

800 26.0 1.138

2.3 Experimental program

in all, 334 runs were carried out with test section

1 in the following ranges of variables:

Heated length

inner diameter

Outer diameter

inlet subcooling

Pressure

Mass velocity

Heat flux

Post-dryout steam quality

7.000 rn

14.9 mm

20. 8 mm

10 + 3 C

30, 50, 70, 100, 120,

140, 160, 180 and 200 bar

500, 1000, 1500, 2000,

2500 and 3000 kg/(M 2 ,s)

10 - 125 W/cm2

0.03 - 1.60

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For each combination of pre ssure and mass velocity

(9 x 6 = 54), 4-8 axial temperature profiles were

.obtained by variation of the heat flux in steps of

5-10 W/CM2 . The maximum obtainable heat flux was

limited by the requirement not to exceed a wall

temperature of about 700 C.

2.4 Tests selected for the assessment

The twenty-five post-dryouts test which were chosen

for the assessment of both MOD2 and MIOD3 of RELAP5

were all obtained with test section No. 1. The

measured data have been published in ref. 2 and

the parameter range covered by the selected tests

is given in Table 3 below.

Table 3

Range of parameters for the selected RIT. experiments.

Measured Outlet steam

Run Pressure Mass flux Inlet temp Heat flux CHF location quality

Ho. MPa kg/rn2,s K kW/m2 m X

136 13.99 1977.0 599.6 509 5.55 0.384

139 14.00 1970.5 600.0 757 2.88 0.608

147 14.00 1494.3 600.0 704 2.88 0.761

154 13.98 1006.6 600.4 552 3.15 0.896

161 13.99 503.2 600.2 405 2.88 1.347

220 10.00 1981.2 574.4 511 *0.324

221 10.01 1973.8 574.2 665 5.55 0.434

224 10.02 1990.3 573.4 860 4.25 0.567

232 10.00 1499.8 573.8 758 4.15 0.673

238 10.01 997.3 572.2 556 4.85 0.740

244 9.98 502.0 573. 405 5.05 1.099

259 6.99 1989.3 549.0 870 6.05 0.510

261 7.02 1988.2 548.4 1053 4.65 0.624

264 6.99 1500.2 547.8 766 6.05 0.598

269 7.01 995.4 547.8 564 *0.667

270 7.02 996.5 547.2 660 5.85 0.785

272 7.02 999.6 547.4 815 4.55 0.977

275 7.04 500.9 547.2 410 6.45 0.980

315 3.01 1986.3 498.0 873 5.95 0.436

317 3.03 1987.3 497.2 1058 5.05 0.532

320 2.99 1499.3 497.6 769 6.05 0.513

325 3.01 1.10.6 496.2 561 *0.554 327 3.00 1005.6 497.2 667 6.05 0.669

331 3.00 497.2 498.6 413 *0.847

1332 1 3.00 1496.4 1497.8 1464 16.25 10.954

The inlet

around 10

temperature was chosen to give sub-cooling

K (Actual range 8.5-1.2.0 K).

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3 Results of previous RELAP5/MOD2 assessment

The assessment of the MOD2 version of RELAPS has

been reported in ref. 1. The geometrical, model,

comprising 47 cells for the heated length of the

testsection, was originally used there and was

adopted also here for the MOD3 simulations.

Two different computations were made with RELAPS/

1M'OD2, a base case simulation with the standard

code version and another in which the code had

been modified to produce a "forced CHF simulation".

3.1 Standard RELAP5/MOD2 simulation

Calculations of the twenty-five RIT test cases

were first made with the original version of RELAP5

/MOD2, cycle 36.02. For all, but two, of the twentyone of the cases in which dryout was measured to

occur, the Biasi-correlation heavily overpredicted

the dryout heat flux. Reasonable agreement was

obtained in two cases only; run No. 136 and 154 at

3 MPa. Large deviations were shown in most cases,

especially with elevated pressures. At 14 NPa the

calculated dryout heat flux could be as much as a

factor of three higher than the experimental

value.

An extended study of Biasi's correlation applied

on 177 RIT experiments in reference 1 revealed a

mean error of 60.B %.

As a consequence of the non-conservative character

of the dryout calculation in RELAP5/MOD2 this version also failed to predict the location of the

onset of dryout. MOD2 generally placed the dryout

downstream the measured position, and in some cases

outside the actual range of the test section, i.e.

no dryout was predicted in cases where dryout was

actually observed in the tests.

3.2 RELAP5/MOD2 forced CHF simulations

in order tEo investigate the capability of RELAPS

to predict post-dryout temperatures when the calculated dryout location agreed with the measured

one, a modification of the code was made and the

simulations were rerun. The update described in

ref. 1 made it possible to specify the CHF point

to coincide with the measurements, causing a shift

in the downstream heat transfer mode.

This modification improved the predictions of the

.post-dryout heat transfer considerably. The discrepancies between predicted and measured temperatuA: LN/RAPP
STUDSVIK NUCLEAR STUDSVIKNUCLEARSTUDSVIK/NS-9 0/93 112

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res were reduced to less than 10 % in all cases

except one (run 139). it was also shown that RELAP5/

MOD2 realistically predicted the steam superheating

observed in the experiments.

A: LN/RAPP
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4 The new critical heat flux model in MOD3

The MOD3 version of RELAP5 incorporates several

modifications compared to MOD2. The changes have

been made in order to improve both the computational

efficiency as well as the capability to model certain phenomena which were unsatisfactory described

in the earlier versions. One of the shortcomings

was the limitations of the Biasi correlation,

which is the only CUF correlation available in

MOD2. Although this correlation is based on tube

data with upwards flow of water, and for a limited

parameter range it is in RELAP5/MOD2 frequently

applied to rod bundles at various flow conditions

occurring, during e.g. a LOCA transient.

However, despite the fact that the Biasi correlation

is based on tube data it failed to predict dryout

in the RIT experiments as shown in ref. 1.

In RELAP5/MOD3 the method of calculating CHF has

been fundamentally changed. The Biasi correlation

has been replaced by a method based on Groeneveld's

"Critical Heat Flux Lookup Table" as described in

ref. 4.' instead of evaluating CHF from an

analytical expression, interpolation is made in a

table which, however, even here is based on test

data for vertical upf low of water in tubes.

The table in I.1D3 has 4410 data points extracted

from 15000 points in the original lookup table,

and form a three-dimensional array with 15 pressure,

14 mass flux and 21 steam quality values covering

the following range:

Pressure 0.1 - 20.0 Mpa

Mass flux 0.0 - 7500 kgl(M 2 ,S)

Steam quality -0.5 - 1.0

In addition to the interpolation, eight multipliers

are applied to account for the influence of hydraulic diameter, rod bundle geometry, direction of

flow, axial heat flux distribution, etc.

Another modification is that the Newton iteration

method in MOD2 to solve for the temperature at CHF

has been replaced by a direct comparison of the

calculated CHF and the actual heat flux. when the

actual heat flux exceeds the MOD3 CHF value the

heat transfer mode changes.

Since the new method *is based on tube data, which

covered the range of the RIT data, good agreement

was expected to be obtained here.

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1990-10-12

5 Input description and geometrical model

The input used in the MQD2 assessment was adopted

here and only changes required by the ?40D3 mnodifications according to ref. 5 were made'. A list of the

input for RIT run 136 is shown in appendix A.

5.1 Geometrical model

The RELAPS model of the experimental

shown in Figure 3 below.

U.0 69 _ 5 _5

0.0 68 T3"-5

6 0 66 _ 5 5

6.10 6.o- ~ ~ -V. ,T

5.05.205 ---- T35-3

3.0_ 4i.ur 3 Z

facility is

*nDP1

45

40

35

30

25

20

is

10

PIPE

VOL

6

5

4

3

2

CELL 5 TMDlPJUN

TDP VOL

Test section and RELAP5 model

A: LN/RAPP
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The test section was modelled with 47 fluid cells.

Large cell lengths were used in the lower part of

the test section because, in the experiments, Cl-F

never occurred below the 2.7 m elevation. The bulk

of the test section was modelled by a uniform

mesh of cells having a length of 10 cm.

Boundary conditions were imposed upon the lower

and upper end of the test section via time dependent volumes. The lower time dependent volume specified the inlet pressure and fluid temperature corresponding to experimental inlet conditions. The

experimental flow rate was specified by a time

dependent junction at the entrance to the test

section.

The heated wall was represented by 47 heat structures (one per fluid volume). Each heat structure

used two heat transfer nodes - one at the wall

inner edge and one at the wall outer edge. A heat

.transfer coefficient (determined by RELAP5) was

specified at the inner wall-edge boundary condition

while the outer wall edge was specified to be completely insulated. The latter specification was

justified by the experimental heat balances which

showed negligible heat loss through the insulation

surrounding the test section.

In order to study the effect of nodalization runs

were also made with reduced number of test section

fluid cells, 22 and 11 cells.

5.2 Changes from MOD2 to MOD3 input

The original MOD2 lines affected by the changes

are left within parenthesis in the input list

(App. A) for comparison.

Flag options are generally set to default or

recommended values. Only those cards which were

affected by the modifications from MOD2 into M.2D3

are commented.

Card No. 201. Time step control card:

Max. time step was generally kept to 0.0025 s as

in MOD2, shorter time steps were used only in a

few cases with convergence problems.

The time step control word W4 was set to 0003

instead of 0011 which meant that a semi-implicit

solution scheme was chosen insted of the nearly-

-implicit scheme for the hydrodynamics. This choice

made no difference to the results, but reduced the

computation time slightly.

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Card No. 1001001, Pipe volume control flags:

The number of control flags have been increased

from two, (fe) to five (pvbfe) and was now set to

11000 instead of 00. in order, the flags mean:

p=1, water packing is not considered, v~l, no

vertical stratififation is taken into account and

b=0, means that the pipe interphase friction model

is applied. fe=00 like in MOD2, that is wall

friction and non-eguilibriumr temperature

calculations are applied.

Card No. 1001101, Pipe junction control flags:

The number of flags has been increased from four

to five. vcahs=3lOOO was changed into fvcahs=O01000.

The new flag f =0 means that CCFL is not taken into

account. Flag v was in 140D2 said to specify horizontal stratification options but is not used in MOD3

and should be set to 0. The flags cahs=0000 were

kept unchanged, which in turn means that the

choking model is used, a smooth area change and a

nonhomogeneous momentum equation.

Card No. 11000801, Heat structure additional left

boundary information:

MOD2 had here a CHF control flag as word 1, but

there was only this option, and the additional

three words were actually not used. In MOD3 this

card is utilized to take into account the effect

of heated length on CHF for short channels (Word 2

and 3, forward and reverse heated lengths, respectively).

The length effect is ignored when a large number

i.e >10 is given which was the case for the RIT

data. Word 4 - 7 is for grid or spacer losses and

was set=0 since there were-*no spacers. Word 8 is a

"local boiling factor" (lbf). According to the

manual (Ref.3) this is local heat flux/average

heat flux from the start of boiling, and is depending on the axial heat flux distribution. Since

uniform heat flux distribution was used in the RIT

tests a value of 1.0 should be used.

Card No. 2000101. 3000101, Time-dependent volume

control flags

Word 9 had 2 digits (fe) in MOD2, but has now 5

digits (pvbfe). However, the first two flags are

not used, the rest have the same implication as in

the pipe input. bfe was now set to 010 meaning

that interphase friction should be calculated, but

not wall friction and that nonequilibrium temperatures are computed.

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Card No. 3500101, Single junction geometry

The control flags, now being six, (fvcahs) were

set to 001000 like in the pipe junction described

before. In the MOD2 input a=l was used which stands

for an abrupt area change instead of a smooth one

with a=0. The difference had no effect on the results.

The discharge coefficients are now three instead

of two in MOD2. A superheat discharge coefficient

has been added to~ the subcooled and two-phase coefficients, and all are set to 1.0. (A value of zero

in MOD2 was by default changed to 1.0)

A: LN /RAPP
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6 Performance of the calculations and

computational efficiency

The-calculations with RELAP5/MOD, versi on m5mn were

run on a SUN Sparc workstation in a network. Some

cases were then run on the server (Sun 330) having

a clock frequency of 16 MHz while most cases were

run on a SUMN workstation with 12 MHz.

The test section power was ramped from zero to

full power in 5 s to reduce the instability a step

function would cause. in this respect MOD3 was

less sensitive than MOD2 for which the ramp period

was set to 10 s and were a too fast ramp switched

over the heat transfer mode into a nonreversible

post-dryout condition far upstream the channel.

The code output announced steady state to be achieved

after in general 10 to 20 s, i.e. 5 to 15 s after

the end of the ramp, with the max. timestep set to

2.5 ins. The table in appenddix B summarizes the

times to reach steady state and the corresponding

computation times for the 47 cell geometry model.

Runs with a reduced number of cells showed that

the computation time was roughly proportional to

the number of cells.

Like in previous MOD2 runs the steady state algoritin

was in many cases found not to be adequate. Stable

flow conditions could be prevailing for a large

number of timesteps before the code decided to

state so, which in some cases was not until the

input end time. in other runs steady state was

proclaimed despite a considerable instability was

seen in the outlet flow. These runs were specially

analyzed regarding the stability in CUF.

The average CPU times per timestep and volume cell

became 6.1 mns and 8.6 mns on the SUN 330 server and

SUN SPARC workstation respectively. This can be

compared with a corresponding average time of 45

mns needed for the MOD2 simulations in ref. 1 on a

CDC Cyber 180-185, in both cases using a max timestep of 2.5 mns.

A: LN/RAPP
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7 Results and data comparison

A summary of the results of the M0D3 simulations

and comparison with measured RIT data and with

earlier MOD2 results from Ref. 1 is given in the

table below.

Table 4

Comparison between experimental and RELAP5 results

Run p o./A 'G Wxal dryout position Max. wall temperature

HPa ~m h9 K

NO. m2 m2 s 1 12 12' 3 1 2 12' 3

136 14 509 1977 5.55 5.70 5.60 5.80 729 735 738 717

139 14 757 1970 2.88 3.50 2.69 3.10 901 835 1024 782

147 14 704 1494 2.88 3.10 2.69 2.96 914 644 895 790

154 14 552 1007 3.15 2.96 2.96 3.20 886 830 830 780

161 14 405 503 2.88 3.60 2,69 3.20 899 880 883 872

220 10 511 1981 * -590 - - 596

221 10 665 1974 5.55 * 5.50 5.90 773 - 777 747

224 10 860 1990 4.25 5.70 4.20 3.90 862 777 851 810

232 10 758 1500 4.15 6.30 4.10 4.20 869 756 845 804

238 10 556 997 4.85 * 4.80 5.50 838 597 806 785

244 10 405 502 5.05 5.70 5.00 5.80 872 820 871 783

259 7 870 1989 6.05 * 6.00 6.80 787 576 802 734

261 7 1053 1988 4.65 6.30 4.60 5.20 874 804 888 809

264 7 766 1500 6.05 * 6.00 6.95 801 576 805 717

269 7 564 995 * - 568 - - 574

270 7 660 996 5.85 * 5.80 *830 576 832 1576

272 7 815 1000 4.55 5.60 4.50 6.50 912 886 1.920 :771

275 7 410 501 6.45 6.60 6.40 6.80 759 749 775 .718

315 3 873 1986 5.95 * 5.80 6.95 834 532 885 739

317 3 1058 1987 6.05 * - 6.95 898 538 - 749

320 3 769 1499 6.05 * 6.00 6.95 .842 531 872 734

325 3 561 1011 * - 6.95 524 - - 526

327 3 667 1006 6.05 * 6.00 6.95 854 528 881 728

331 3 413 497 * -521 - - 711

3321 3 1464 1 496 16.25 16.70 16.20 16.80 1 827 799 1880 1749

Notes: Cohaimn 1 measured

2 =calculated with RMULS5MOD2 (IIDD2.5)

2t=_It_ It- , mdified version (Ref. 1)

3 =-$I- R!L3P5A9O33

* No dryout measured or calculated

Plotted results i.e. inner wall temperatures versus

axial position are shown in Appendix D.1-D.21 for

runs in which dryout occurred.

Ref.1 contained only data of the modified MOD2 calculations, i.e. the cases where the onset of dryout

had been adjusted to coincide with the experimental

dryout point (Column 2' above). The MOD2 results

(Column 2).were therefore regenerated using the

original input but with RELAP5/MOD2.5. This can be

justified as !40D2.5 and !40D2 employ identical CHF

models based on the Biasi correlation and also the

same post-dryout heat transfer models.

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1990-10-12

7.1 Critical Heat Flux prediction

The results show that the new CHF method in MOD3

generally gave a better prediction of the dryout

axial location than the original 140D2 method. The

onset of dryout was by MOD2 calculated to take

place at a point considerably far downstream the

measured point, in all cases but one (Run 154, App.

D.4). MOD2 predicted no dryout to occur in as many

as nine cases in which drycut was really observed

in the experiments.

The new critical heat flux model in M'OD3 resulted

in only one case (Run 270) in which dryout was predicted not to take place contrary to the measurements.

However, the dryout axial location was still placed

more or less downstream the experimentally observed

point for most of the analyzed cases. only in run

224 did RELAP5/MOD3 compute a dryout point upstream

the observed position.

In runs at moderate pressures, 3 and 7 MPa, and for

cases in which the dryout took place only about one

meter from the testsection exit, the RELAP5/MOD3

model gave dryout in the uppermost 0.05 m long cell

only. (In neither of these cases did M'1D2 predict

dryout). Hoee, MOM0D should not have predicted

dryout either, nor have shifted the heat transfer

mode into post CHF mode (from mode 4 to 8) since

the calculated CHF-value was still larger than the

actual local heat flux.

The erraneous dryout prediction was an effect of

the location in an exit cell, which was demonstrated

by rerunning some cases with the test section.lengthened by four extra outlet cells. This check revealed

that the axial position for the onset of dryout

moved with the number of exit cells, still into the

uppermost one. Table 4 therefore shows a false indication of dryout for the position 6.95 m (Run Nos.

264, 315, 317, 320, 325 & 327).

The stability of the dryout predicted by RELAP5/MOD3

is illustrated in figs. 4 to 7. Fig. 4 and 5 show

the time history of the outlet mass flow compared

with the inlet flow for run 147 and 261. Fig 6 and

7 show the calculated critical heat flux (HTCHF)

compared with the actual input heat flux (HTRNR)

for the same cases. For both the code message was

that stady state was achieved, although the outlet

mass flow was steady in run 147, but oscillated

considerably in run 261. However, stable CHF was

reached within less than 1 s after the end of the

ramp for both runs.

A: LN/RAPP
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1990-10-12

RIT run 147 06.6'

0.5-

0.4 -

;60.3-

0.2 -

Outlel

0.0 I I ii I

1.0 2.0 3.0 4.0 5.0

Tune (s)

6.0 7.0 8.0 9.0 10.0

Fig. 4 Mass flow rate at test section inlet (tmdpjun 250)

and at outlet (snqljun 350) in run RIT 147

Rrr run 261

0 La

0.

0.'

S0..

*1 K. met 5 . '

4-I

2- U

0.:

0.

. 0 -0 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0

Time (s)

10.0

Fig. 5 Mass flow rate at test section inlet (tmdpjun 250)

and at outlet (snallun 350.) in run JUT 261

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1990-10-12

Rfl run 147

2.5e+06

2e+06 -

lo1+06-

SODOaOao -

Lz.-RENJ

0. I I I I I I ~l I T

0.0 1.0 2.0 3.'0 4.0 5.0 6.0 7.'0 8.0 9.0

Time (s)

10.0

Fiq. 6 Actual inside wall heat flux (HTRNR) and calculated

critical heat flux (HTCHF) in cell No. 7 for run 147

RrT run 261

26+06 -

10+.06-

0. 0 -&.= -

0.0 1 .0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0

TITI (3)

Fia. 7I Actual inside wall heat flux (HiTRNR) and calculated

critical heat flux (HTCHF) in cell No. 29 for run 261

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The fact that the calculated dryout point often

appeared downstream the experimentally observed

point means that the new CHF method in RELAPS/MOD3

is still non-conservative compared with the RIT

data. The calculated critical heat flux is thus

higher than the experimental one, as shown in table

5 below. Comparison is there made between calculated

and measured dryout heat flux at the experimentally

observed dryout location for RELAP5/MOD2.5 and

/MOD3 respectively. The error E is defined thus:

(gIA) c- (gIA)

E(q/A) -l1

Table 5

Comparison between predicted and experimental

dryout heat flux

Run p (q/A)m G Zm 25 3

MPa kW k

No. M2 mPS

,136 14 509 1977 5.55 0.30 0.11

139 14 757 1970 2.88 0.64 0.24

147 14 704 1494 2.88 0.46 0.19

154 14 552 1007 3.15 < 0 0.12

161 14 405 503 2.88 0.49 0.86

220 10 511 1981 - -

221 10 665 1974 5.55 0.62 0.23

224 10 860 1990 4.25 0.28 -0.10

232 10 758 1500 4.15 0.54 0.04

238 10 556 997 4.85 1.21 0.30

244 10 405 502 5.05 1.16 0.58

259 7 870 1989 6.05 0.62 0.36

261 7 1053 1988 4.6~5 0.42 0.29

264 7 766 1500 6.05 0.82 0.58

269 7 564 995 *- -

270, 7 660 996 5.85 0.96 0.99

272 7 815 1000 4.55 0.78 0.77

275 7 410 501 6.45 0.42 0.97

315 3 873 1986 5.95 2.26 2.20

317 3 1058 1987 6.05 1.18 0.92

320 3 769 1499 6.05 2.56 2.28

325 3 561 1011 *- -

327 3 667 1006 6.05 2.52 2.45

331 3 .413 497 *- -

1332 13 1464 1496 16.25 1 1.06 11.32

* No dryout measured or calculated

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The error in predicted dryout heat flux seem to

increase with decreasing pressure as illustrated by

Fig. 8. The lines representing the mean errors show

that the new method in M'1D3 is in fact not any radical improvement compared with MOD2 for the RIT data.

200.0-

-v 100.0

50.0-

C

0'0

450.01S m "(P)i 2.0 4.0 6.0 8.0 10.0 12.0 14.0 16.

Fig. B Error in predicted CHF with RELAP5/MOD2 and MOD3

related to measured CHF

7.2 Post-dryout heat transfer

The pre-CHF heat transfer predicted by RELAPS agree

reasonably well with the experiments. The wall temperatures from ?40D3 are equal or slightly higher than

those calculated with MOD2. Both RELAP5 versions

give higher wall temperatures than the expertimental

values. The measured pre-CHF inner wall temperatures

reported in ref. 2 seem, however, to be somewhat

low compared to fluid saturation temperatures. This

is especially the case at high pressures which can

be due to uncompensated heat losses.

The post-CHF wall temperatures show much larger

deviations from the experimental values. In this

region the occurance of small constant errors in

the measured temperatures are negligible compared

with the large temperature differences between

inner wall and coolant.

RELAP5/MOD3 gives noticeably lower temperatures

than RELAP5/MOD2 did and less good agreement with

the measurements in the post-dryout region. This

means that MOD3 uses a larger convective heat transfer coefficient than MOD2 does. A comparison can be

made for run 147, at 14 MPa, in which there was a

reasonable good agreement between predicted and

measured dryout location (App. C.3a). The following

ranges were obtained for the convective heat transfer coefficient in the post CHF region:

RELAPB/MOD2, 3196 - 5883 W/(m 2 ,C)

RELAP5/MOD3, 4506 - 6026-"

Experiment, 2475 - 7699--

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1990-10-12

The low values apply to the immediate post-dryout

region, and the heat transfer is then growing towards

the exit as the steam quality and thus the fluid

velocity increases.

in order to make a relevant comparison of the heat

transfer calculations in MOD2 arnd MODM the point of

onset of dryout should be correct, or at least egual

for the two versions. With the modified MOD2 runs

[Ref. 1) the experimental dryout point was forced

into the computations. A similar modification wasnot employed here. Instead, the lbf factor was used

to adjust the calculated critical heat flux to be

equal to the actual heat flux at the dryout point.

The lbf number, intended to account for effects of

a non-uniform axial heat flux distribution, just

acts as another correction factor for the CUF. It

was in this case used to obtain a lower total CHF

multiplier. The effect of varying the lbf-f actor

from 1.0, the recommended value, to 0.5 for run 261

is shown in Fig. 9. The corresponding CHF multiplier

then decreased proportionally from 0.82 to 0.41

arI run 261

1000.0

900.0

E........................................ ........

I-'PffSM(.rt-1.0I R 

RELAPS MoM3. 3t-0S -....

8. 00.0- tRELAPSMod3. RX-3I

.. RLAPSMOM V0.5

7000 I

600.0 .

0.0 0.5 1.'0 1.S 2.0 2. 3.0 3.5 4.0 4.5 50 6.5 6.0 635 7.0

Fig.9 Effect of the lbf-factor in RELAP5/MOD3 on calculated

inner wall temperatures for run 261

The cases in which the dryout point has been adjusted

in this way are included for comparison in Appendices

D.5 and D.10 (runs 161 and 244). Provided that the

axial positions of the beginning of the'post-dryout

region are egual, it is obvious that RELA2P5/MOD3

calculates much lower wall temperayures than RELAP5/

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MOD2. The 140D2 heat transfer model gave a satisfactory prediction of the maximum temperature when the

location of the dryout point was correct, as shown

in Table-4 (Column 21).

it is evident that the convective heat transfer

calculational method has been changed from 140D2 to

MOD3, giving too large convective heat transfer

coefficients. The reason for this is unclear as

long as no model desription or program manual was

available at this moment.

7.3 Nodalization studies

it was shown in ref. 1 that the sensitivity in

calculated inner wall temperature for changes in

the number of radial nodes in the tube wall-was

small. Differences less than 0.5 K were seen between

runs with two nodes, as in the base cases, and with

ten nodes. Since the heat conduction models are not

changed, the same conclusion should be valid for

results with RELAP/MOD3 as for /MOD2, and therefore

only runs with two radial-nodes were performed here.

The effect of the number. af axial fluid cells was,

however, examined. Case RIT 232 was chosen, for

which there was good agreement in the calculated

dryout position with 47 cells. This nodalization

employes cell lengths as short as 0.05 m, that is

much finer than is normally used in reactor calculations, where lengths of about 0.5 m are commonly

used. Therefore runs were performed also with 22

and 11 cells, i.e. with' minimum cell lengths 0.25

and 0.5 m respectively.

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1990-10-12

Fig. 10 shows that, except for the coarser resolution around the dryout point, there is not much

difference in the post-dryout wall temperatures.

The disturbance effect of the erraneously calculated

exit-cell temperature becomes, however more pronounced with a longer exit cell (which can be avoided

by adding an extra outlet cell).

9

C

Axial level (in)

Fig.1O Effect of axial nodalization on inner wall

temperature in run 232

7.4 Calculations on experiments with non-uniform

axial heat flux distributions

A number of new post-dryout experimental data has

been produced at the Royal Institute of Technology

in Stockholm in which the effect of various axial

heat flux distributions have been studied (Ref. 3).

The axial power shapes simulate realistic distributions in power reactors but some with larger form

factors.

Same tentative calculations were made on a few

experiments with symmetric distributions and form

f actors around 1.6. Comparison with experimental

data underlined the same trend as with the earlier

assessment, i.e. RELAP5/MOD3 overpredicted the CHF

considerably. In fact, the trend seemed to be more

pronounced with the non-uniform data. At low pressures RELAP5/MOD3 was not able to predict CHF at all

even when high post-dryout temperatures were measured.

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1990-10-12

8 Conclusions

Reassessment has been performed of R.ELAP5 against

twenty-five RIT post-dryout experiments, now with

version MOD3 5m5 compared to the earlier assessment

with version MQD2 cycle 36.02. The following conclusions were drawn:

1. The new dryout calculational method in MOD3,

based on "Groenevelds look-up tables" gave

better prediction of the dryout heat flux

than the method in MOD2, based on Biasi's

correlation. Thereby was also an improved

prediction of the location of the onset of

dryout achieved.

2. The improvement in the dryout calculation is

still not satisfactory compared with the

measured RIT data. A considerable overprediction is left. For the cases in which dryout

occurred the mean error was reduced only

from 96 to 74 per cent from MOD2 to 140D3,

related to the measured dryout, heat flux

The standard deviation became allmost unchanged, about 70 per cent, indicating a

large degree of uncertainty.

3. There seem to-be a pressure dependence of the

error in calculated CHF. The overprediction

being around 20 per cent at high pressures

-increases to as much as a factor of three

at 3 MPa.

4. An effect of overpredicted CHE is that the

onset of drycut is calculated to take place

far downstream the experimentally observed

point in most cases. As a conseguence of

this RELAP5IMOD3, like M'1D2, underpredicts

the post-dryout wall temperatures.

5. Even in cases where the error in the dryout

axial location is small, or when the dryout

point is forced to coincide with the experimental one (by adjusing the lbf-f actor), the

calculated post-dryout wall temperatures

with MOD3 are remarably lower than measured

values. This is especially noticed irmmediately

downstream the drycut point where MOM3 gives

still lower temperatures than MOD2. The difference to measured temperatures decreases

then towards the channel exit as the steam

superheat increases.

6. The changes of the post-dryout heat transfer

models, which have obviously been done-from

MOD2 into MOD3, have impaired the agreement

compared with the RIT experimental data.

A: LN/RAPP
STUDSVIK NUCLEAR ST1JDSIK. NCLEARSTUDSVIK/NS-90/ 93 229

1990-10-12

With heat transfer mode 8 (saturated film

boiling) the heat transfer coefficients in

MOD2 gave in general wall temperatures within

10 per cent of observed values, mostly overpredictions at low and underpredictions at

high pressures.

All heat transfer coefficients have become

larger for 140D3 in this region. since the

model description has not been released for

MOD3, no further analysis of modifications

or the background for the changes is made

here.

7. A nodalization study showed little effect of

the number of axial fluid cells in the range

11 to 47 cells on the wall temperature.

However, there is a disturbance from the

uppermost cell resulting in a increase of

the temperature calculated in this cell.

8. The computational efficiency has probably

been improved compared with MOD2. One reason

might be that the CHF calculation in MOD2

employed an iteration for the wall

temperature which in MOMD is replaced by a

direct comparison of calculated CHF and

actual surface heat flux. (Comparison of CPU

times for the present and the previous

assessment is not relevant since different

types of computers were used)

There is still an inconsistency in the steady

state convergence criterion like in MOD2.

A: LN/RAPP
STUDSVIK NUCLEAR STUDSIK NULEARSTUDSVIK/NS-90/93 330

199 0-10-12

References

I SJ65BERG, A. and CARAHER, D

ICAP. Assessment of RELAP5/MOD2 against

twenty five dryout experiments conducted

at the Royal Institute of Technology.

Studsvik Report STUDSVIK/NP-86/66

2 BECKER, K.M., et. al.

An experimental investigation of post

dryout heat transfer

KTH-NEL -33. Royal Institute of Technology,

Stockholm, May 1983

3 BECKER, K.M. et. al.

Post dryout heat transfer measurements in

vertical round ducts with non-uniform

axial heat flux distributions.

Royal Institute of Technology, Stockholm

Report in progress

4 SHUNWAY, R.

New critical heat flux method for RELAP5IMOD2

EGG-EAST-8443 (Informal Report)

EGG&G Idaho Inc., Idaho Falls, Jan. 1989

5 Appendix A. RELAP5 input data requirements.

Prepared for release of RELAP5/MOD3.

EG&G Idaho Inc. Idaho Falls, Idaho, Jan. 1990

A: LN/RAPP
STUDSVIK NUCLEAR .STUDSVIK/NS-90/93 31

1990-10-12

List of tables

Page

1 ICAP Assessment Matrix - Sweden 4

2 Thermal properties of test section wall

material 9

3 Range of parameters for the selected

RIT experiments 10

4 Comparison between experimental and

RELAPS results 19

5 Comparison between predicted and

experimental dryout heat flux 23

A: LN /RAPP
STUDSVIK NUCLEAR STUDSVIK/NS-90/93 32

1990-3 0-12

List of figures

Page

1 Test loop flow diagram 5

2 Location of thermocouples in test

section 1 and 2 8

3 Test section and RELAP5 model 14

4 Mass flow at test section inlet and

outlet in run 147 21

5 Mass flow at test section inlet and

outlet in run 261 21

6 Actual inside wall heat flux and calculated CHF in cell No. 7 for run 147 22

7 Actual inside wall heat flux and calculated CHF in cell No. 29 for run 261 22

B Error in predicted CHF with RELAP5/MOD2

and MOD3 related to measured CHF 24

9 Effect of the lbf-f actor in RELAP5/MOD3

on calculated inner wall temperatures

in run 261 25

10 Effect of axial nodalization on inner

wall temperatures in run 232 27

A: LN/RAPP
STUDSVII( NUCLEAR STUDSVIK/NS-90/93 Appendix A.1 (5)

1990-10-12

RELAP5/Mod3/5m.5 RIT PDO-case 136

Canged Mod2 input lines within C

*This case is a simulation of a post dry-out experiment

*conducted by K.M. Decker et al. in tbe N~uclear Engineering

Laboratory at the Royal Institute of Technology (RIT) in

*Stockholm and is reported in ref (2). The test section *comprised a seven meter long heated vertical pipe with wall

*thermocouples located throughout the heated length. The

*inner diameter was 0.0149 m.

*The experiment was run with time-invariant boundary conditions

*with an Uniform axial power distribution and the data were *recorded when the conditions in the test section were stable.

*The constant boundary conditions for the case number 136 were:

*outlet pressure 13.99 mpa

* maaflux1976.C kg/u2/s

T n&flette~mperature 599.65 k

* heat flux 0.509 mw/g.2

*The test section was modeled as a pipe component with 47

*volumes The heated wall was modeled by using conducting *materiali with a cylind~rical geometry including two mesh

*points, one on each surface. The inner surface was connected *to the bydro-dynamic pipe volumes through the beat transfer

*package while the outer surface was assumed completely insulated. CChecking of heat balance was part of the experimental routine

*and revealed an insignificant level of beat losses to the

Cambient thus justifying the assumption of the insulated outer

*surface.

CReference 1 K.M. Becker

* )An experimental investigation of post dryout

* heat transfer

* RKTB-NEL-33

* Department of Nuclear Reactor Engineering

* Royal Institute of Technology

* Stockholm, Sweden

May 1983

0000100 new stdy-st

0000101 run

*CPU time remaining card

0000105 10.0 20.0

Ctime step control cards

*time-end dt-min dt-max asdxx min-edit maj-edit restart

0000201 8.0 1.Oe-6 0.0025 00003 OD 2000 4000

(5 time-end dt-min dt-max ssdxx cmm-edit maj-edit restart) )4002

(0000201 0.1 l.Oe-6 0.0025 00011 s0 2000 4000)

*minor edit requests

0000301 cputime 0 * CPU-time

0000302 p 100010000 * inlet nods pressure

0000303 p 100470000 * outlet node pressure

0000304 voidg .100200000 * outlet node void fraction

0000305 voidgj 350000000 * outlet junc. void fraction

0000306 tempf 100470000 * outlet node tempf

0000301 tempg 100470000 * outlet node tempg

0000308 sattemp 100470000 * outlet node t-.at

0000309 httemp 100000101 * wall temp t04

0000310 httemp 100000501 * wall temp t12

0000311 httemp .100001001 * wall temp t17

0000312 httemp 100001501 * wall temp t22

0000313 bttemp ,100002001 * wall temp t27
STUDSVII< NUCLEAR STUDSVIK/PS-90/93 Appendix A'.2 (5)

1990-10-12

0000314 bttemp 100002501 * wall tamp t32

0000315 bttemp 100003001 * wall tamp t37

0000316 bttemp 100003501 * wall temp t42

0000317 bttemp 100004001 * wall temp t49

0000318 bttemp 100004501 * wall tamp t54

0000319 btrnr 100000100 * beat flux

0000320 btrnr 100000500 * beat flux

0000321 btrnr 100001000 * beat flux

0000322 btrnr 100001500 * beat flux

0000323 btrnr. 100002000 * beat flux

0000324 btrnr 100002500 * beat flux

0000325 btrnr 100003000 * beat flux

0000326 btrnr 100003500 * beat flux

0000327 btrnr 100004000 * beat flux

0000328 btrnr 100004500 * beat flux

0000329 btcbf 100000100 * critical beat flux

0000330 btcbf 100000500 * critical beat flux

0000331 btcbf 100001000 C critical beat flux

0000332 htcbf 100001500 C critical beat flux

0000333 btcbf 100002000 C critical beat flux

0000334 btcbf 100002500 * critical beat flux

0000335 btcbf 100003000 * critical beat flux

0000336 btcbf 100003500 * critical beat flux

0000337 btchf 100004000 * critical beat flux

0000338 bt~cbf 100004500 * critical beat flux

0000339 btbtc 100000100 * btc

0000340 btbtc 100000500 * btc

0000341 btbtc 100001000 * btc

0000342 btbtc 100001500 * btc

0000343 btbtc 100002000 C btc

0000344 btbtc 100002500 * btc

0000345 btbtc 100003000 C btc

0000346 btbtc 100003500 * btc

0000347 btbtc 100004000 * btc

0000349 btbtc 100004500 * btc

0000349 floreg 100010000 * flow regime number

0000350 floreg 100050000 C flow regime number

0000351 florog .100100000 * flow regime number

0000352 floreg 100150000 * flow regime, number

0000353 floreg 100200000 * flow regime number

0000354 flaorg 100250000 * flow regime number

0000355 floreg 100300000 * flow regime number

0000356 floreg 100350000 * flow regime number

0000357 floreg 100400000 * flow regime number

0000358 floreg 100450000 * flow regime number

0000359 mflowj 250000000 * inflow inlet

0000360 mflovj 350000000 * =nflow outlet

C *CCCChydrodynamic componentsCCC

C tbe beated pipe is modeled an a pipe component nr 200'

1000000 bot-cbs pipe

*nvol

1000001 47

Carea nvol

1000101 1.14366e-04 411

Clongtb nvol

1000301 0.750 1

1000302 0.500 5

1000303 0.250 6

1000304 0.100 45

1000305 0.050 47

CV-angle nvol

1000601 90.0 47
STUDSVIK NUCLEAR STIJDSVIE/NS- 90/93 Appendix A.3 (5)

1000801

1001001

(1001001

1001101

(1001101

1990-10-12

rough d-hyd nvol

20.0e-06 0.0149 47

pipe volume control flags

pvhfe nvol

11000 47

fe nvol) ?AOD2

00 47)

pipe junction control flags

fvcabs nvol-l

001000 46

vcahs nvol-1) 140D2

31000 46)

1001201 0C

ct

1001300 1

ain

1001301 3.

Lpe volue Initial conditions

At pressure temp. dummyl

03 13.99e+06 599.65 0.0

dumny2 dummy3 nvol

0.0 0.0 47

Lpe junction data

:rl-wrd

itial cond.

Low-f flow-g

,4465e-1 0.0

flow-fg njunc

0.0 46

a a~ *

*

11000000

a

* eat structure data * *

nh

47

np type ss-fl lcoord

2 2 1 7.45&-03

* 1c fmt

11000100 0 1

anint. - rcoord

11000101 1 1.04e-02

*composition - interval

11000201 1 1

11000301

11000400

11000401

11000501

11000502

11000503

11000504

11000505

11000601

12000602

11000603

11000604

11000605

11000701

11000702

11000703

11000704

11000705

4

11000801

source - Interval

1.0 1

tflq

0

initenp for each beat-str.

initemp mesh

599.65 2

bndvol incr

100010000 010000

100020000 010000

100060000 010000

100070000 010000

100460000 010000

bndcon

1

1

1

1

1

sac

1

1

1

1

1

factor

0.750

0.500

0.250

0.200

0..050

0.750

0.500

0.250

0.100

0.050

bsnr

1

5

6

45

47

1

5

6

45

47

" lef t

" left

a left

" left

" left

" right

" right

" right

" right

" right

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

1

1

1

1

1

arctyp

1

1

1

1

1

mult

0.750

0.500

0.250

0.100

0.050

dhl

0.0

0.0

0.0

0.0

0.0

dhr

0.0

0.0

0.0

0.0

0.0

hanr

45

47

do hif blr

0 20.0 10.0

grid factors

0.0 0.0 0.0

lbf bsnr

0.0 1.0 47

chf

(11000801 0

de dh length bonr)

0.0 0.0 0.0 47)

HMfl2
STUDSVII( NUCLEAR STUDSVIK/NS-90/93 Appendix A.4 (5)

1990-10-12

*bea structure th. prop. composition is nimonic 75 *mat~erial-type for-figl for-flg2

20100100 tbllfctn 1

*temp. tb.cond.

20100101 270.0 12.0

20100102 5000.0 93.4

*vol.heat-cap.

20100151 4.0e406

*general table for beat structure power Csrctyp 1)

*tbl-type trip tactor-t. factor-p

20200100 power 0 1.0 1.0

*time linear power (vim)

20200101 0.0 0.0

20200102 5.0 23.8262*+03

20200103 20.0 23.8262e+03

* **end of beat structure data *

*lover boundary condition

otmdpvol - component 200

*tadpjuri - component 250

2000000 lo-bndry tmdpvol

*area length vol. b-angle v-angle a1ev. rough d-hyd pvbfe

2000101 1.0 1.0 0.0 0.0 90.0 1.0 0.0 1.0 00010 area length vol. b-angle v-angle *elv. rough d-byd to) bfOD2

(2000101 1.0 1.0 0.0 0.0 90.0 1.0 0.0 1.0 10)

o bt tbl-nr

2000200 003 0

*time pressure temp.

2000201 0.0 13.99e406 599.65

2500000 lo-flov tmdpJun

Cfrom-code to-code area

2500101 200000000 100000000 0.0

*ctrl-wrd

2500200 1

*time flow-f flov-g flov-fg

2500201 0.0 3.4465e-l 0.0 0.0

u pper boundary condition

*tadpvol - component 300

a ng1jun - cqmponent 350

3000000 up-bndry tmdpvol

*area length vol. b-angle v-angle elev. rough d-byd pvbfe

3000101 1.0 1.0 0.0 0.0 90.0 1.0 0.0 1.0 00010

area length vol. b-angle v-angle elov. rough d-byd to) 14002

(3000101 1.0 1.0 0.0 0.0 90.0 1.0 0.0 1.0 10)

o bt tbl-nr

3000200 003 0

*time pressure temp.

3000201 0.0 13.99*406 100.0
STUDSVIK NUCLEAR STUDSVIK/NS-90/93 Appendix A.5 (5)

1990-10-12

*

*

*

*

3500000 up-flow £r~g1jun S

3500

(3500101

3500201

from-code

100010000

from-code

100010000

to-code area

300000000 0.0

to-code area

300000000 0.0

f-loss

0.0

f-loss

0.0

r-loss

0.0

r-loss

0.0

fvcahs dis-coaffs.

001000 1.0 1.0 1.0

vcabs dis-cooffs.) MOD2

31100 0.0 0.0)

cv flow-f flow-9

I 3.4465e-1 0.0

flow-fg

0.0

end of case

STUDSVIK NUCLEAR STUDSVIK STUDSVIK/NS-90 NUCLEAR /93 Apnippendix B.1.

P.17 RELAP5/Mod3 runs. CPU-times on SUN system

47 cell model

Run dt-max

(s)

time to s.s.

(s)

cputime time steps

(s) No.

136 0.0025 17.9975 2739.6 7199

139 0.0025 20.0000 2624.1 8000

147 0.0025 10.0000 1256.7 4000

154 0.0025 12.7100 1599.9 5084

161 0.0025 13.9125 2412.9 5565

220 0.0025 11.7775 1417.2 4711

221 0.0025 12.4375 2099.9 4975

224 0.0025 20.0000 3832.3 8613

232 0.0025 12.4375 2193.4 4975

238 0.0025 11.7775 2011.3 4711

244 0.0025 14.3975 2456.0 5759

259 0.0025 17.1100 2405.8 8134

261 0.0025 10.0000 * 2017.6 6456

264 0.0025 17.6832 2089.7 7236

269 0.0025 19.3800 2233.S 7752

270 0.0025 13.2425 1520.3 5297

272 0.0025 11.2925 1496.7 5057

275 0.0025 13.0175 1534.4 5207

315 0.0010 10.4985 2587.6 8883

317 0.0010 30.0000 * 10005. 34012

320 0.0025 10.5675 2328.1 7975

325 0.0025 25.0000 ** 5454.7 18730

327 0.0025 17.6700 3710.3 12784

331 0.025 25.0000 * 4186.6 13832

332 0.0025 10.1450 1715.1 5642

Notes: *Outlet flow not stable, steady state claimed to be reached

~'Steady state not achieved, termin~ated by end of time card,

however, relatively stable Outlet flow

Average CPU-time per timeatep and cell - 6.1 ms on SUN 330 server

- 8.6 =s on SUN SPARC workstation

STUDSVIK NUCLEAR STUDSVIK STUDSVIK/NS-90/ NUCLEAR 93 AperdxC1(5 Apppendix C-1 (25)

1990-10-12

JUT run 136

inside wall temperatures, T (K) versus axial levelZ' (mn)

Experiment R'ELAP5- resu its

z

0.05

0.25

0.50

0.75

1.00

1.25

1 .50

1.75

2.00

2.25

2.50

2.75

3.00

3.1

3.2

3.3

3.4

3.5

3.6

3.7

3.8

3.9

4.0

4.1

4.2

4.3

4.4

4.5

4.6

4.7

4.8

4.9

5.0

5.1

5.2

5.3

5.4

5.5

5.6

5.7

5.8

5.9

6.0

6.1

6.2

6.3

6.4

6.5

6.6

6.7

6.8

6.9

6.95

T

611.2

611.4

611.7

609.7

610.6

610.4

609.9

610.8

610.5

610.1

608.4

608.9

608.4

608.3

609.0

608.9

608.5

608.0

606.7

609.0

608.3

608.9

608.9

608.9

609.3

609.4

609.4

607.3

608.5

609.9

609.0

609.4

609.4

610.0

609.6

610.1

607.2

610.6

658.5

706.9

718.2

723.6

725.5

726.4

729.1

727.4

727.8

728.9

727.2

724.3

722.7

721.5

717.3

2

0.375

1.00

1.50

2.00

2.50

2 .875

3.05

3.35

3.25

3.35

3.45

3.55

3.65

3.75

3.85

3.95

4.05

4.35

4.25

4.35

4.45

4.55

4.65

4.75

4.85

4.95

5.05

5.15

5.25

5.35

5.45

5.55

5.65

5.75

5.85

5.95

6.05

6.15

6.25

6.35

6.45

6.55

6.65

6.75

6.85

6.925

6.975

MOD3

T

619.58

620.24

620.52

620.52

620.33

620.12

620.01

619.95

619.88

619.82

619.75

619.65

619.55

619.46

619.36

619.27

619.18

619.10

619.01

618.93

618.85

618.77

618.69

618.62

618.54

618.47

618.40

618.33

618.26

618.19

618.13

618.06

618.00

617.94

682.78

688.23

693.90

699.38

703.34

706.41

708.95

710.87

712.28

713.29

714.10

7112.96

716.59

MOD2

T

614.34

614.57

614.65

614.85

615.14

615.25

615.29

615.34

615.39

615.44

615.49

615.54

615.59

615.63

615.68

615.72

615.77

615.81

615.86

615.90

615.94

615.98

616.03

616.07

616.11

616.15

616.19

616.21

616.31

616.46

616.58

616.68

616.75

718.70

722.68

726.07

729.00

731.40

733.20

734.40

734.80

734.43

733.79

732.83

732.04

730.74

730.61

MOD2 mod.

T

614.3

614.6

614.6

614.8

615.1

615.2

615.3

615.3

615.4

615.4

615.5

615.5

615.6

615.6

615.7

615.7

615.8

615.8

615.9

615.9

615.9

616.0

616.0

616.1

616.1

616.1

616.2

616.2

616.3

616.4

616.6

616.6

721.7

725.8

729.2

732.2

734.7

736.5

737.7

737.8

737.4

736.6.

735.6

734.4

733.4

732.0

731.8

A: LN /RAPP
STUDSVIK NUCLEAR STUDSVIK/NS-90/93 STUDVIKNUCLAR Apppendix TUDSIK/S-9 /93 C.2 (2$)

1990-10-12

RIT run 139

Inside wall temperatures. T (K) versus axial level. z (mn)

Experiment

z

0.05

0.25

0.50

0.75

1.00

3 .25

1.50

1.75

2.00

2.25

2.50

2.75

3.00

3.1

.3.2

3.3

3.4

3.5

3.6

3.7

3.8

3.9

4.0

4.1

4.2

4.3

4.4

4.5

4.6

4.7

4.8

4.9

5.0

5.1

5.2

5.3

5.4

5.5

5.6

5.7

5.8

5.9

6.0

6.2

6.2

6.3

6.4

6.5

6.6

6.7

6.8

6.9

6.95

T

611.3

610.9

612.1

609.1

610.1

609.9

609.4

610.2

609.3

609.6

607.8

608.3

625.8

856.3

885.8

884.5

881.6

886.1

885.4

901.1

897.4

899.8

895.5

891.2

886.7

881.3

873.3

855.3

848.1

838.6

828.0

818.3

809.7

800.8

793.3

775.5

768.5

759.9

751.2

744.5

738.5

730.2

726.9

720.2

717.0

715.1

710.3

705.5

702.6

698.4

693.3

RELAP5-results

M0D3

z T

0.375 623.19

1.000 623.68

1.500) 623.81

2.000 623.61

2.500 623.10

2.875 622.54

3.05 622.30

3.15 737.37

3.25 748.77

3.35 759.07

3.45 765.85

3.55 771.35

3.65 775.50

3.75 778.66

3.85 780.72

3.95 781.89

4.05 782.31

4.15 782.12

4.25 781.43

4.35 780.38

4.45 779.08

4.55 777.62

4.65 776.05

4.75 774.42

4.85 772.76

4.95 771.10

5.05 769.45

5.15 767.82

5.25 766.21

5.35 764.64

5.45 763.11

5.55 761.61

5.65 760.16

5.75 758.74

5.85 757.37

5.95 756.04

6.05 754.74

6.15 753.49

6.25 752.28

6.35 751.10

6.45 749.97

6.55 748.87

6.65 747.81

6.75 ý746.77

6.85 745.88

6.925 743.68

6.975 746.96

MOD2

T

615.94

616.04

616.61

617.18

617.77

617.99

618.06

618.17

618.29

618.36

618.62

804.98

820.49

832.22

833.86

834.88

834.43

832.35

829.42

825.97

822.15

818.09

813.90

809.65

805.41

801.23

797.14

793.15

789.29

785.56

781.97

778.52

775.21

772.03

769.00

766.09

763.31

760.66

758.12

755.69

753.38

751.16

749.08

746.94

745.39

743.39

743.66

MOD2 mod.

T

616.0

616.0

616.6

617.2

617.8

943.3

958.0

978.0

996.5

1013.

1024.

1024.

1010.

983.8

948.6

921.8

901.4

884.4

870.2

858. 1

847.6

838.2

830.0

822.5

815.8

809.6

804.0

798.8

793.9

789.4

785.1

781.1

777.4

773.8.

770.5

767.4

764.4

761.6

758.9

756.4

754.0

751.6

749.5

747.3

745.7

743.7

744.0

A:LN/RAPP
STUDSVIK PUCLEAR STUDSVIK STUDSVIK/NS-90/93 NUCLEAR ApedxC3(5 Apppendix C.3 (25)

1990-10 -12

BIT run 147

Inside wall temperatures, T (K) versus axial level,z (mn)

Experiment RELAP5-results

MOD3

z

0.05

0.25

0.50

0.75

1.00

1.25

1 .50

1.75

.2.00

2.25

2.50

2.75

3.00

3.1

3.2

3.3

3.4

3.5

3.6

3.7

3.8

3.9

4.0

4.1

4.2

4.3

4.4

4.5

4.6

4.7

4.8

4.9

5.0

5.1

5.2

5.3

5.4

5.5

5.6

5.7

5.8

5.9

6.0

6.1

6.2

6.3

6.4

6.5

6.6

6.7

6.8

6.9

6.95

T

611.0

611.3

611.5

609.5

610.5

610.3

609.8

610.6

610.4

610.0

608.2

610.0

815.3

894.5

913.6

906.7

902.7

906.5

899.7

911.8

905.5

904.3

899.4

894.5

889.4

882.8

875.4

858.1

853.5

842.1

832.7

823.6

816.8

808.6

801.8

785.8

779.4

771.5

762.8

756.8

745.9

742.5

739.8

733.1

730.5

727.4

723.2

719.7

716.2

712.6

706.9

z

0.375

1.000

1.500

2.000

2.500

2.875

3.05

3.15.

3.25

3.35

3.45

3.55

3.65

3.75

3.85

3.95

4.05

4.15

4.25

4.35

4.45

4.55

4.65

4.75

4.85

4.95

5.05

5.15

5.25

5.35

5.45

5.55

5.65

5.75

5.85

5.95

6.05

6.15

6.25

6.35

6.45

6.55

6.65

6.75

6.85

6.925

6.975

T

622.32

623.03

623.26

623.15

622.85

622.52

744.40

755.32

765.34

771.30

776.39

780.22

783.49

786.10

788.07

789.45

790.20

790.37

790.07

789.41

788.47

787.32

786.02

784.63

783.19

781.72

780.25

778.79

777.35

775.94

774.57

773.23

771.94

770.69

769.49

768.33

767.22

766.17

765.17

764.22

763.31

762.45

761.64

760.87

760.08

759.12

760.51

MOD2

T

615.80

616.18

616.90

617 .65

618.60

619.27

619.58

810.11

823.26

835.51

840.79

843.67

844.34

843.31

841.30

838.53

835.20

831.42

827.41

823.29

819.15

815.03

810.99

807.04

803.22

799.53

795.99

792.60

789.36

786.26

783.32

780.52

777 .85

775.33

772.93

770.66

768.51

766.49

764.57

762.76

761.07

759.45

757.99

756.47

755.54

753.77

754.47

MOD2 mod.

T

615.8

636.2

616.9

617.6

618.6

889.5

894.6

893.4

890.8

887.3

882.4

876.8

870.8

864.6

858. 3

852.1

846.1

840.2

834.5

829.0

823.8

818.9

814.1

809.6

805.4

801.3

797.5

793.8

790.4

787.2

784.1

781.2

778.4

775.8

773.3

771.0

768.8

766.8

764.8

763.0

761.2

759.6

758.1

756.6

755.7

753.9

754.6

A: LN/RAPP
STUDSVIK NUCLEAR STUDSVIK STUDSVIK/NS-90/93 NUCLEAR ApedxC4(5 Apppendix C.4-(25)

1990-10-12

RIT run 254

inside wall temperatures, T (K) versus axial level,z (in)

Experiment

z

0.05

0.25

0.50

0.75

1.00

1.25

1.50

.1.75

2.00

2.25

2.50

2.75

3.00

3.1

3.2

3.3

3.4

3.5

3.6

3.7

3.8

3.9

4.0

4.1

4.2

4.3

4.4

4.5

4.6

4.7

4.8

4.9

5.0

5.1

5.2

5.3

5.4

5.5

5.6

5.7

5.8

5.9

6.0

6.1

6.2

6.3

6.4

6.5

6.6

6.7

6.8

6.9

6.95

T

611.7

611.6

610.2

621.1

610.3

609.8

611.3

610.4

610.6

608.9

608.8

608.9

608.2

673.5

774.4

812.7

831.6

846.4

856.6

868.7

877.2

882.1

884.8

886 .2

883.8

875.0

870.3

862.8

855.9

848.6

843.1

836.8

831.2

817.8

812.7

806.7

799.3

793.8

784.3

782.1

778.9

772.2

769.7

766.5

762.4

758.3

754.2

751.2

745.6

RELAPS-results

MOD3

z T

0.375 619.57

1.000 620.45

1.500 621.11

2.000 621.15

2.500 622.02.

2.875 620.87

3.05 620.79

3.15 620.75

3.25 736.24

3.35 745.25

3.45 753.44

3.55 758.58

3.65 761.68

3.75 764.03

3.85 765.68

3.95 766.97

4.05 768.23

4.15 769.57

4.25 770.92

4.35 772.29

4.45 773.72

4.55 775.12

4.65 776.39

4.75 777.50

4.85 778.43

4.95 779.14

5.05 779.63

5.15 779.90

5.25 779.99

5.35 779.94

5.45 779.77

5.55 779.50

5.65 779.17

5.75 778.81

5.85 778.42

5.95 778.02

6.05 777.63

6.15 777.25

6.25 776.90

6.35 776.59

6.45 776.32

6.55 776.07

6.65 775.89

6.75 775.75

6.85 775.76

6.925 774.04

6.975 778.38

MOD2

T

615.00

615.59

616.37

617.52

619.19

619.87

793.39

805.51

817.64

823.84

827.95

829.80

830.34

829.91

828.57

826.64

824.34

821.76

819.02

816.17

813.26

810.35

807.49

804.71

802.01

799.42

796.94

794.58

792.33

790.19

788.18

786.29

784.51

782.85

781.30

779.86

778.53

777.32

776.21

775.21

774.31

773.50

772.85

772.13

772.04

770.63

771.72

MOD2 mod.

T

625.0

615.6

616.4

617.5

619.0

619.7

792.2

805.1

817.3

823.6

827.8

829.7

830.3

829.9

828.6

826.7

824.4

821.8

819.1

816.2

813.3

810.4

807.6

804.8

802.1

799.5

797.0

794 .6

792.4

790.2

788.2

786.3

784.6

782.9

781.3

779.9

778.6

777.4

776.2

775.2

774.3

773.5

772.9

772.2

772.0

770.6

771.7

A: LN /RAPP
STUDSVIK NUCLEAR STUDVIKNUCEARSTUDSVIK/NS-90/93 -Apppendix C.5 (25)

199 0-10-12

RIT run 161

Inside wall temperatures, T (K) versus axial level~z (in)

Experi~ment RELAP5-results.

MOD3

lbf=3 .0 z z T

0.05

0.25

0.50

0.75

1.00

1.25

1.50

1.75

2.00

2.25

2.50

2.75

3.00

3.1

3.2

3.3

3.4

3.5

3.6

3.7

3.8

3.9

4.0

4.1

4.2

4.3

4.4

4.5

4.6

4.7

4.8

4.9

5.0.

5.1

5.2

5.3

5.4

5.5

5.6

5.7

5.8

5.9

6.0

6.1

6.2

6.3

6.4

6.5

6.6

6.7

6.8

6.9

6.95

T

611.2

611.5

611.7

610.4

611.9

611.1

610.6

611.4

611.2

611.4

612.8

613.2

630.4

'796.2

817.9

832.2

845.0

854 .1

869.5

871 .2

877.8

882.0

884.4

887.2

890.3

891.5

894.9

897.4

897.8

897.5

897.5

898.7

89-7.8

898.9

895.7

896.1

894.9

893.0

891.2

893.1

888.5

888.9

885.9

887.6

886.8

886.9

887.7

887.2

889.1

883.5

0.375

1 .000

1.500

2.000

2.500

2.875

3.05

3.15

3.25

3.35

3.45

3.55

3.65

3.75

3.85

3.95

4.05

4.15

4.25

4.35

4.45

4.55

4.65

4.75

4.85

4.95

5.05

5.15

5.25

5.35

5.45

5.55

5.65

5.75

5.85

5.95

6.05

6.15

6.25

6.35

6.45

6.55

6.65

6.75

6.85

6.925

6.975

616.82

617.79

618.49

628.89

619.08

619.09

619.07

619.06

619.05

734.40

744.44

754.85

761.38

766.90

771.15

774.53

777.17

779.09

780.34

781.05

781.39

781.52

781.61

781.77

782.17

782.88

784.00

785.59

787.68

790.32

793.51

797.26

801.61

806.48

812.06

518.11

823.84

829.37

834.83

840.24

845.63

851.01

856.23

861.38

866.58

867.87

87 1'.77

MOD3

lbf=0. 75

T

616.82

617.79

618.49

628.89

619.08

619.09

742.08

753.58

764.21

771.24

776.92

781.60

785.36

788.44

790.77

792.42

793.42

793.97

793.97

793.55

792.85

792.05

791.29

790.74

790.53

790.74

791.45

792.73

794.61

797.11

800.25

804.08

808.54

813.82

819.66

825.16

830.42

835.61

840.75

845.85

850.93

855.90

860.77

865.61

870.53

871.66

874.54

MOD2

T

614.55

635.34

616.64

618.81

619.07

619.10

619.09

619.08

619.07

619.06

619.05

619.04

732.22

743.44

755.80

765.03

773.27

780.58

787.21

793.24

798.76

803.81

808.40

812.60

816.45

820.00

823.30

826.39

829.34

832.10

834.77

837.43

840.12

842.85

845.56

848.22

850.91

853.72

856.64

859.69

862.90

866.25

869.76

873. 15

876.98

877.53

880.25

HOD2 mod.

T

614.6

615.3

616.6

618.8

619.1

803.6

808.6

817.5

824.'3

829.7

8334.9

837.0

839.4

841.2

842.4

843.2

843.7

844.0

844.2

844.3

844.3

844.4

844.5

844.7

844.9

845.1

845.5

846.1

846.8

847.6

848.7

849.9

851.2

852.6

854 .1

855.8S

857.7

859.8

862.1

864.6

867.3

870.2

873.2

876.1

879.7

880.0

882.6

A: LN/RAPP
STUDSVIK NUCLEAR STUDSVIK/NS-90/93 STUDV1KNUCLAR Apppendix TUDVIK/S-9/93 C.6 (25)

1990-10-12

JUT run 220

Inside wall temveratures. T MK versus axial level.z (m)

Experiment

z T

0.05 588.1

0.25 588.3

0.50 588.6

0.75 587.8

1.00 588.8

1.25 588.5

1.50 588.1

1.75 588.3

2.00 588.0

2.25 588.7

2.50 589.0

2.75 588.9

3.00 589.0

3.1 587.0

3.2 587.7

3.3 587.6

3.4 586.6

3.5 587.4

3.6 587.3

3.7 589.0

3.8 587.6

3.9 587.6

4.0 587.6

4.1 588.3

4.2 588.0

4.3 588.1

4.4 588.1

4.5 587.9

4.6 588.5

4.7 588.6

4.8 588.3

4.9 588.1

5.0 588.1

5.1 588.7

5.2 587.8

5.3 588.2

5.4 587.2

5.5 588.1

5.6 588.5

5.7 588.5

5.8 588.4

5.9 587.8

6.0 588.5

6.1 588.7

6.2 589.1

6.3 589.1

6.4 589.6

6.5 589.5

6.6 589.6

6.7 589.7

6.8 589.9

6.9 589.9

6.95 588.5

RELAPS/MQD3

z

0.375

1.000

1.500

2.000

2.500

2.875

3.05

3.15

3.25

3.35

3.45

3.55

3.65

3.75

3.85

3.95

4.05

4.15

4.25

4.35

4.45

4.55

4.65

4.75

4.85

4.95

5.05

5.15

5.25

5.35

5.45

5.55

5.65

5.75

5.85

5.95

6.05

6.15

6.25

6.35

6.45

6.55

6.65

6.75

6.85

6.925

6.975

T

595.79

596.55

596.69

596.46

596.05

595.69

595.52

595.42

595.32

595.21

595.11

595.00

594.87

594.75

594.63

594.52

594.41

594.30

594.19

594.09

593.98

593.88

593.79

593.69

593.60

593.50

593.41

593.32

593.24

593.15

593.07

592.99

592.90

592.82

592.75

592.67

592.59

592.52

592.44

592.37

592.30

592.23

592.16

592.09

592.03

591.98

591.95

A: LN/RAPP
STUDSVIK NUCLEAR STUDSVIK/NS-90/93 STUDVIKNUCLAR Appperidix TUDVIK/S-9/93 C.7 (25)

1990-10 -12

RIT run 221

Inside wall temperatures. T (K) versus axial level~z (mn)

Experiment RELAP5-results

MNOD

z

0.05

0.25

0.50

0.75

1.00

1.25

1.50

1.75

2.00

2.25

2.50

2.75

3.00

3.1

3.2

3.3

3.4

3.5

3.6

3.7

3.86

3.9

4.0

4.1

4.2

4.3

4.4

4.5

4.6

4.7

4.8

4.9

5.0

5.1

5.2

5.3

5.4

5.5

5.6

5.7

5.8

5.9

6.:0

6.1

6.2

6.3

6.4

6.5

6.6

6.7

6.8

6.9

6.95

T

589.1

589.3

589.6

588.2

589.1

588.9

587.8

588.6

588.4

588.0

589.4

589.9

589.3

586.7

587.5

587.4

587.0

587.1

587.6

589.3

587 .4

587 .4

588.0

589.2

588.4

588.5

589.1

588.8

588.8

589.0

589.3

588.5

589.1

589.1

.586.9

584 .3

581.3

584.8

589.5

635.7

695.4

745.8

753.3

762.6

769.7

770.3

771.4

773.1

772.0

767.9

768.0

768.7

761.2

z

0.375

1 .000

1.500

2.000

2.500

2.875

3.05

3.15

3.25

3.35

3.45

3.55

3.65

3.75

3.85

3.95

4.05

4.15

4.25

4.35

4.45

4.55

4.65

4.75

4.85

4.95

5.05

5.15

5.25

5.35

5.45

5.55

5.65

5.75

5.85

5.95

6.05

6.15

6.25

6.35

6.45

6.55

6.65

6.75

6.85

6.925

6.975

T

598.54

599.13

599.122

598.71

598.12

597.57

597.28

597.11

596.96

596.80

596.66

596.51

596.37

596.24

596.10

595.97

595.85

595.72

595.60

595.49

595.37

595.26

595.15

594.94

594.83

594.73

594.63

594.54

594.45

594.36

594 .27

594.19

594.10

594.02

714.36

721.47

727.51

732.35

736.18

739.03

741.09

742.47

743.25

743.75

741.86

746.85

MOD2

T

591.39

591.69

592.38

593.01

593.59

593.77

593.79

593.88

593.97

594 .14

594.35

594.55

594.77

594.97

595.12

595.24

595.36

595.48

595.59

595.63

595.52

595.40

595.30

595.19

595.08

594.98

594 .88

594.78

594.68

594.59

594.50

594.40

594.31

594.22

594.14

594.05

593.97

593.88

593.80

593.72

593.64

593.56

593.49

593.41

593.34

593.27

593.24

MOD2 mod.

T

591.4

591.7

592.4

593.0

593.6

593.8

593.8

593.9

594.0

594.2

594.4

594.5

594.7

594.8

594.9

595.0

596.1

596.2

595.3

595.4

595.5

595.4

595.3

595.2

595.1

595.0

594.9

594.8

594.7

594.6

594.5

758.4

765.5

770.5

774.0

'776.0

776.9

777.1

776.6

775.6

774.2

772.5

770.7

768.5

767.0

764.5

764.6

A: LN /RAPP
STUDSVIK NUCLEAR STUDSVIK/NS-90/93 STUDVIKNUCLAR Apppendix TUDVIK/S-9/93 C.8 (25)

1990-10-12

RIT run 224

Inside wall temperatures., T (K~) versus axial level,z (mn

Experiment

z

0.05

0.25

0.50

-0.75

1.00

1.25

1.50

1.75

2.00

2.25

2.50

2.75

3.00

3.1

3.2

3.3

*3.4

3.5

3.6

3.7

3.8

3.9

4.0

4.1

4.2

4.3

4.4

4.5

4.6

4.7

4.8

4.9

5.0

5.1

5.2

5.3

5.4

5.5

5.6

5.7

5.8

5.9

6.0

6.1

6.2

6.3

6.4

6.5

6.6

6.7

6.8

6.9

6.95

T

589.3

589.6

589.8

587.8

588.8

588.5

588.1

588.9

588.0

588. 3

589.6

590.1

589.0

585.1

586.5

587.0

586.0

586.7

587.3

589.0

587 .0

587.0

587.6

585.1

584.2

603.7

729.4

825.1

849.7

857.8

862. 5

861.1

861.1

861.0

857.6

855.6

846.9

841.7

836.2

828.1

821.9

812.2

808.2

804.8

798.1

794.9

789.9

785.0

777.2

773.6

768.1

758.1

RELAPS-results

MON0D

z T

0.375 601.52

1.000 602.06

1.500 601.92

2.000 601.30

2.500 600.27

2.875 599.46

3.05 599.12

3.15 598.94

3.25 598.76

3.35 598.59

3.45 598.42

3.55 598.26

3.65 598.10

3.75 597.95

3.85 597.80

3.95 775.82

4.05 787.28

4.15 796.20

4.25 802.60

4.35 806.75

4.45 809.11

4.55 810.12

4.65 810.07

4.75 809.30

4.85 808.02

4.95 806.40

5.05 804.56

5.15 802.57

5.25 800.50

5.35 798.40

5.45 796.28

5.55 794.18

5.65 792.10

5.75 790.06

5.85 788.07

5.95 786.12

6.05 784.23

6.15 782.39

65.25 780.61

6.35 778.88

6.45 777.20

6.55 775.57

6.65 773.99

6.75 772.45

6.85 771.15

6.925 767.87

6.975 767.56

MOD2

T

592.77

593.53

594.55

595.58

596.81

597.55

597.66

597.89

598.11

598.34

598.55

598.39

598.23

598.08

597.93

597.79

597.64

597.51

597.37

597.24

597.11

596.99

596.86

596.75

596.63

596.52

596.40

596.30

596.18

596.09

595.97

595.89

595.76

752.13

759.42

765.32

769.75

772.92

775.30

776.46

777.13

777 .24

777.02

776.24

775.90

773.81

774 .78

MOD2 mod.

T

592.8

593.6

594.6

595.6

596.8

597.3

597 .4

597.6

597.8

598.0

598.3

598.4

598.2

598. 1

598.0

597.8

597.7

597.5

826.8

837.5

844.6

848.7

850.5

850.7

849.6

847.6

844.8

841.5

837.9

834.2

830.4

826.5

822.6

818.9

815.1

811.5

808.0

804.6

801.3

798.1

795.1

792.1

789.4

786.5

784.5

781.5

782.0

A: LN/RAPP
STUDSVIK NUCLEAR STUDSVIK STUDSVIK/NS-90/93 NUCLEAR ApedxC9(5 Apppendix C.9 (25)

1990-10-12

RIT run 232

Inside wall temperatures, T (K) versus axial level..z (mn)

Experiment

z

0.05

0.25

0.50

0.75

1.00

1.25

1.50

1.75

2.00

2.25

2.50

2.75

3.00

3.1

3.2

3.3

3.4

3.5

3.6

3.7

3.8

3.9

4.0

4.1

4.2

4.3

4.4

4.5

4.6

4.7

4.8

4.9

5.0

5.1

5.2

5.3

5.4

5.5

5.6

5.7

5.8

5.9

6.0

6.1

6.2

6.3

6.4

6.5

6.6

6.7

6.8

6.9

6.95

T

588.6

588.8

589.1

587. 1

588.7

587.8

587.3

588.2

587.9

588.2

589.5

589.4

588.3

584.4

585.8

585.6

584.0

581.0

579.7

582.0

581.3

581.9

582.5

584 .4

592.2

657.8

824.7

833.0

854 .4

861.9

868.4

868.1

868.8

869.3

867.2

865.8

858.3

853.8

848.3

841.3

836.6

827.5

823.5

820.2

814.7

811.5

807.7

802.9

796.3

792.2

786.8

776.8

RELAP5-results

MOD3

z T

0.375 599.53

1.000 600.51

1.500 600.49

2.000 600.04

2.500 '599.41

2.875 598.80

3.05 598.50

3.15 598.33

3.25 598.17

3.35 598.02

3.45 597.87

3.55 597.72

3.65 597.58

3.75 597.45

3.85 597.31

3.95 597.18

4.05 597.06

4.15 596.93

4.25 763.63

4.35 774.30

4.45 783.15

4.55 790.20

4.65 795.53

4.75 799.31

4.85 801.78

4.95 803.24

5.05 803.94

5.15 803.97

5.25 803.54

5.35 802.77

5.45 801.76

5.55 800.58

5.65 799.28

5.75 797.90

5.85 796.47

5.95 795.03

6.05 793.61

6.15 792.20

6.25 790.81

6.35 789.46

6.45 788.16

6.55 786.90

6.65 785.69

6.75 784.52

6.85 783.56

6.925 780.70

6.975 786.16

HOD2

T

592.19

593.30

594 .47

596.05

598.29

598.91

598.59

598.42

598.26

598.11

597.96

597.81

597.67

597.53

597.40

597.27

597.15

597.02

596.90

596.79

596.67

596.56

596.46

596.35

596.25

596.15

596.05

595.96

595.87

595.78

595.69

595.61

595.52

595.44

595.36

595.29

595.20

595.15

595.05

724.77

732.01

738.38

743.89

748.49

752.72

753.35

755.79

MQD2 mod.

T

592.2

593.3

594 .5

596.0

597.9

598.6

598.6

598.4

598.3

598.1

598.0

597 .8

597 .7

597.6

597.4

597.3

597 .2

813.7

825.4

833.9

839.7

843.2

844.0

845.4

844.6

843.2

841.2

838.8

836.0

833.1

830.1

827.0

824.0

820.9

818.0

815.1

812.3

809.6

806.9

804.4

802.0

799.7

797.6

795.2

793.8

791.1

792.0

A: LN/RAPP
STUDSVIK NUCLEAR STUDSVIK/NS-90/93 STUDVIKNUCLAR Apppendix TUDVIK/S-9/93 C.10 (25)

1990-10-12

HIT run 238

Inside wall temveratures. T MK versus axial level.z (inl

Experiment

z

0.05

0.25

0.50

0.75

1.00

1.25

1.50

1.75

2.00

2.25

2.50

2.75

3.00

3.1

3.2

3.3

3.4

3.5

3.6

3.7

3.8

3.9

4.0

4.1

4.2

4.3

4.4

4.5

4.6

4.7

4.8

4.9

5.0

5.1

5.2

5.3

5.4

5.5

5.6

5.7

5.8

5.9

6.0

6.1

6.2

6.3

6.4

6.5-

6.6

6.7

6.8

6.9

6.95

T

588.4

588.7

588.9

587.5

588. 5

588.3

587.8

588. 0

588.4

588.0

589.3

589.2

588.7

584.9

585.6

583.6

582.7

582.2

583.1

583.0

583.6

583.6

584.3

584.0

584.1

584.8

583.9

583.9

584.0

586.8

704.3

783.5

801.0

812.2

821.1

831.9

837.1

837.7

837.6

838.2

834.7

836.1

837.1

835.3

834.6

833. 8

832.1

828.6

825.7

824.1

815.9

RELAP5-results

MOD3

z T

0.375 595.81

1.000 596.83

1.500 597.54

2.000 597.49

2.500 597.18

2.875 596.89

3.05 596.75

3.15 596.67

3.25 596.59

3.35 596.51

3.45 596.43

3.55 596.35

3.65 596.27

3.75 596.19

3.85 596.12

3.95 596.04

4.05 595.97

4.15 595.89

4.25 595.82

4.35 595.74

4.45 595.67

4.55 595.58

4.65 595.49

4.75 595.41

4.85 595.32

4.95 595.24

5.05 595.17

5.15 595.09

5.25 595.02

5.35 594.95

5.45 594.88

5.55 723.70

5.65 731.70

5.75 739.14

5.85 745.98

5.95 752.13

6.05 757.59

6.15 762.36

6.25 766.45

6.35 769.95

6.45 772.91

6.55 775.40

6.65 777.48

6.75 779.24

6.85 780.85

6.925 779.58

6.975 785.37

?fOD2

T

591.00

592.00

593.18

594.74

596.98

596.94

596.79

596.71

596.63

596.55

596.48

596.40

596.32

596.24

596.17

596.09

596.02

595.94

595.87

595.80

595.73

595.64

595.55

595.47

595.38

595.31

595.23

595.15

595.08

595.01

594.94

594.88

594.81

594.75

594.69

594.64

594.58

594.53

594.48

594.43

594.38

594.34

594.30

594.26

594.23

594.18

594.17

MOD2 mod.

T

591.0

592.0

593.2

594.7

596.6

597.0

596.8

596.7

596.7

596.6

596.5

596.4

596.3

596.3

596.2

596.1

596.0

596.0

595.9

595.8

595.8

.595.7

595.6

595.5

760.3

770.7

779.4

786.5

792.1

796.6

799.9

802.3

804 .0

805.1

805.7

805.9

805.8

805.5

805.0

804.4

803.6

802.8

802.0

800.9

800.6

798.5

799.7

A:LN/RAPP
STUDSVIK NUCLEAR STUDSVIK/NS-90/93 Apppendix C.11 (25)

1990-10-12

RIT run 244

Inside wall temperatures Tj ~versus axial level,.?_(r)

Exoerixnent RELAPS-resul ts

MOD3

z

0.05

0.25

0.50

0.75

1.00

1.25

1.50

1.75

2.00

2.25

2.50 ý2.75

3.00

3.1

3.2

3.3

3.4

3.5

3.6

3.7

3.8

3.9

4.0

4.1

4.2

4.3

4.4

4.5

4.6

4.7

4.8

4.9

5.0

5.1

5.2

5.3

5.4

5.5

5.6

5.7

5.8

5.9

6.0

6.1

6.2

6.3

6.4

6.5

6.6

6.7

6.8

6.9

6.95

T

589.1

589.4

589.6

588.9

589.2

588.4

587.3

587.5

587.9

588. 1

588.8

588.7

588.8

585.0

584.5

584.4

583.4

583.5

578.5

583.9

583.8

583.8

585.0

584.4

584.8

.584.9

584.9

584.0

584.0

584.1

584.5

584.3

584.9

685.0

747.6

767 .9

775.9

793.6

804.8

812.0

818.4

825.6

831.2

835.0

842.6

846.8

852.1

856.7

861.6

866.0

869. 1

872.2

867.2

z

0.375

1.000

1.500

2.000

2.500

2.875

3.05

3.15

3.25

3.35

3.45

3.55

3.65

3.75

3.85

3.95

4.05

4.15

4.25

4.35

4.45

4.55

4.65

4.75

4.85

4.95

5.05

5.15

5.25

5.35

5.45

5.55

5.65

5.75

5.85

5.95

6.05

6.15

6.25

6.35

6.45

6.55

6.65

6.75

6.85

6.925

6.975

T

592.46

593.62

594.34

594.66

594.76

594.71

594.65

594.62

594.59

594.56

594.53

594.49

594.46

594.43

594.40

594.37

594.34

594.31

594.29

594.26

594.24

594.21

594.19

594.17

594.16

594.14

594.13

594.12

594.12

594.11

594.12

594.12

594.14

594.16

710.69

'717.39

723.64

729.69

735.71

741.78

747.95

754.30

760.89

767.73

'774.84

778.16

782.60

MOD2

T

590.24

591.45

592.97

594.68

594.78

594.74

594.68

594.65

594.62

594.59

594.55

594.52

594.49

594.46

594.43

594.40

594.38

594.35

594.32

594.30

594.28

594.25

594.23

594.22

594.20

594.19

594.18

594.17

594.16

594.17

594.17

594.18

594.19

712.79

722.55

732.20

741.76

751.20

760.51

769.65

778.62

787.38

795.94

804.19

812.40

815.29

819.50

MOD2 mod.

T

590.2

591.5

593.1

594.7

594.8

594.8

594 .7

594.7

594.6

594.6

594.6

594.5

594.5

594.5

594.4

594.4

594.4

594.4

594.3

594.3

594.3

594.3

594.2

594.2

594.2

594.2

731.5

742.9

753.8

764.3

774.3

783.8

792.8

801.3

809.3

816.8

823.8

830.4

836. 5

842.3

847.7

852.8

857.7

862.1

866.9

867.6

870.7

A: LN/ RAPP
STUDSVIK NUCLEAR STUDSVIK/HS-90/93 STUDVIKNUCLAR Apppendix TUDVIK/S-9/93 C.12 (25)

1990-10-12

RIT run 259

Inside wall temperatures. T M1 versus axial level.z (m)~

Experiment RELAP5-results

MOD3

0.05

0.25

0.50

0.75

1.00

1.25

1.50

1.75

2.00

2.25

2.50

2.75

3.00

3.1

3.2

3.3

3.4

3.5

3.6

3.7

3.8

3.9

4.0

4.1

4.2

4.3

4.4

4.5

4.6

4.7

4.8

4.9

5.0

5.1

5.2

5.3

5.4

5.5

5.6

5.7

5.8

5.9

6.0

6.1

6.2

6.3

6.4

6.5

6.6

6.7

6.8

6.9

6.95

T

566.7

567.6

567.9

565.2

566.2

565.3

564.8

565.7

564.8

565.0

567.0

566.9

566.4

563.1

563.9

564.4

562.7

562.2

563.4

563.9

562.5

562.5

562.5

560.0

559.7

558.6

558.6

559.0

557.7

557.8

558.2

558.6

558.6

559.2

558.8B

558.7

557.0

557.3

557.1

557.1

556.9

558.2

561.4

573.1

580.3

624.6

755.0

772.1

778.4

779.8

785.4

786.7

779.8

z

0.375

2 .000

1.500

2.000

2.500

2.875

3.05

3.15

3.25

3.35

3.45

3.55

3.65

3.75

3.85

3.95

4.05

4.15

4.25

4.35

4.45

4.55

4.65

4.75

4.85

4.95

5.05

5.15

5.25

5.35

5.45

5.55

5.65

5.75

5.85

5.95

6.05

6.15

6.25

6.35

6.45

6.55

6.65

6.75

6.85

6.925

6.975

T

578.75

579.20

578.59

577.48

576.04

575.06

574.65

574.42

574.20

573.99

573.78

573.58

573.39

573.20

573.01

572.83

572.66

572.49

572.33

572.17

572.01

571.85

571.70

571.55

571.40

571.25

571.11

570.97

570.83

570.69

570.55

570.42

570.29

570.16

570.03

569.90

569.78

569.65

569.53

569.41

569.29

569.17

569.05

568.94

725.46

728.69

733.51

MOD2

T

569.76

571.22

572.66

574.32

576.15

575.39

574.94

574.71

574.49

574.27

574.07

573.87

573.68

573.49

573.30

573.12

572.95

572.77

572.61

572.44

572.28

572.12

571.97

571.82

571 .67

571.52

571.38

571.24

571.10

570.96

570.83

570.70

570.57

570.44

570.31

570.18

570.06

569.94

569.82

569.70

569.58

569.46

569.35

569.23

569.13

569.02

568.98

MOD2 mod.

T

569.8

571.3

572.7

574.2

575.7

575.4

575.0

574.7

574.5

574.3

574 .1

573.9

573.7

573.5

573.3

573.2

573.0

572.8

572.6

572.5

572.3

572.2

572.0

571.8

571.7

571.6

571.4

571.3

571 .

571.0

570.9

570.7

570.6

570.5

570.3

570.2

778.1

786.5

792.8

797.1

799.8

801.4

802.2

802.0

802.1

799.5

800.8

A: LN/RAPP
STUDSVIK NUCLEAR STUDSVIK/NS-90/93 STUDVIKNUCLAR Apppendix TUDVIK/S-9/93 C.13 (25)

199 0-10-12

RIT run 261

Tnside wall temoeratures. T (K) versus axial level, z (in)

Experiment

z

0.05

0.25

0.50

0.75

3.00

1.25

1.50

1.75

2.00

2.25

2.50

2.75

3.00

3.1

3.2

3.3

3.4

3.5

3.6

3.7

3.8

3.9

4.0

4.3

4.2

4.3

4.4

4.5

4.6

4.7

4.8

4.9

5.0

5.1

5.2

5.3

5.4

5.5

5.6

5.7

5.8

5.9

6.0

6.1

6.2'

6.3

6.4

6.5

6.6

6.7

6.8

6.9

6.95

T

567 .9

568.8

569.3

565.7

566.7

565.8

565.4

566.2

565.3

565.6

568.2

568. 1

566.9

563.0

564.4

564.9

562.6

562.1

563 .9

564.4

563.0

563.0

562.4

559.8

559.6

557.8

558.4

556.9

558.8

577.3

595.9

734.5

845.2

859.4

867.2

872.7

873.8

872.9

868.6

862.8

857.2

854 .1

845.0

843.1

836.9

833.0

829.1

823.0

813.2

812.1

806.0

794.0

RELAP5-results

MOD3

z T

0.375 581.83

1.000 582.27

1.500 581.40

2.000 579.79

2.500 578.06

2.875 577.00

3.05 576.55

3.15 576.30

3.25 576.06

3.35 575.83

3.45 575.61

3.55 575.40

3.65 575.19

3.75 574.99

3.85 574.79

3.95 574.60

4.05 574.41

4.15 574.22

4.25 574.04

4.35 573.86

4.45 573.69

4.55 573.52

4.65 573.35

4.75 573.19

4.85 573.03

4.95 572.87

5.05 572.71

5.15 572.56

5.25 774.22

5.35 784.19

5.45 792.10

5.55 798.34

5.65 802.76

5.75 805.87

5.85 807.90

5.95 809.04

6.05 809.45

6.35 809.34

6.25 808.84

6.35 808.05

6.45 807.04

6.55 805.89

6.65 804.65

6.75 803.34

6.85 802.18

6.925 798.84

6.975 805.18

MOD2

T

571 .87

573.80

576.14

579.17

578.52

577.37

576.87

576.61

576.37

576.14

575.92

575.70

575.49

575.28

575.08

574.89

574.69

574.51

574.33

574.15

573.97

573.80

573.64

573.47

573.31

573.15

573.00

572.85

572.70

572.55

572.41

572.27

572.13

571.99

571.85

571.73

571.58

571.47

571.31

771.25

780.12

787.55

793.31

797.60

801.50

800.93

803.64

MOD2 mod.

T

571.9

573.9

.576.1

578.6

578.6

577.4

576.9

576.7

576.4

576.2

576.0

575.8

575.6

575.4

575.2

-575.0

574.8

574.6

574.4

574 .2

574.0

573.9

859.7

871.9

879.8

884.6

887 .1

887.5

886.5

884.6

882.0

878.9

875.6

872.0

868.3

864.6

860.8

857.1

853.5

849.9

846.4

843.0

839.9

836.5

834.3

830.4

831.4

A:LN/RAPP
STUDSVIK NUCLEAR STUDSVIK/NS-90/93 STUDVIKNUCLAR App-pendix TUDVIK/S-9/93 C.14 (25)

1990-10-12

RIT run 264

Insde allter~ertures., T (K)..versus axial 1evelz)

Exneriment

z

0.05

0.25

0.50

0.75

1.00

1.25

1:50

1.75

2.00

2.25

2.50

2.75

3.00

3.1

3.2

3.3

3.4

3.5

3.6

3.7

3.8

3.9

4.0

4.1

4.2

4.3

4.4

4.5

4.6

4.7

4.8

4.9

5.0

5.1

5.2

5.3

5.4

5.5

5.6

5.7

5.8

5.9

6.0

6.1

6.2

6.3

6.4

6.5

6.6

6.7

6.8

6.9

6.95

T

567.0

567 .9

568.1

566.1

566.4

566.2

565.1

565.9

565.1

565.3

567.3

567.2

566.7

563.4

564.8

564.7

563.7

562.5

564.3

564.2

562.8

562.8

560.9

560.3

560.0

558.9

559.5

559.9

559.3

560.0

560.4

560.1

559.5

559.5

559.1

559.0

558.5

558.9

558.6

558.6

558.5

559.1

562.3

589.5

684 .8

760.0

775.8

786.7

792.3

794.3

799.3

801.2

794.9

RELAPS-results

MOD3

2. T

0.375 576.43

1.000 577.51

1.500 577.19

2.000 576.35

2.500 575.39

2.875 574.56

3.05 574.18

3.15 573.97

3.25 573.77

3.35 573.58

3.45 573.39

3.55 573.21

3.65 573.03

3.75 572.86

3.85 572.69

3.95 572.52

4.05 572.36

4.15 572.21

4.25 572.06

4.35 571.91

4.45 571.76

4.55 571.62

4.65 571.49

4.75 571.35

4.85 571.23

4.95 571.10

5.05 570.97

5.15 570.85

5.25 570.73

5.35 570.61

5.45 570.49

5.55 570.37

5.65 570.26

5.75 570.15

5.85 570.04

5.95 569.93

6.05 569.82

6.15 569.72

6.25 569.62

6.35 569.52

6.45 569.42

6.55 569.32

6.65 569.22

6.75 569.13

6.85 569.04

6.925 568.96

6.975 716.81

MOD2

T

569.20

570.84

572.70

575.19

575.64

574.79

574.37

574.16

573.96

573.76

573.57

573.39

573.21

573.04

572.87

572.71

572.55

572.40

572.24

572.10

571.95

571.81

571.67

571.54

571.41

571.28

571.15

.571.03

570.91

570.79

570.67

570.56

570.45

570.34

570.23

570.12

570.02

569.91

569.82

569.71

569.62

569.52

569.43

569.33

569.25

569.16

569.13

MOD2 mod.

T

569.2

570.9

572.7

574.8

575.7

574.8

574.4

574.2

574 .0

573.8

573.6

573.4

573.2

573.1

572.9

572.7

572.6

572.4

572.3

572.1

572.0

571.8

571 .7

571.6

571.4

571.3

571.2

571.0

570.9

570.8

570.7

570.6

570.5

570.4

570.2

570.1

768.6

778.1

785.8

791.6

796.1

799.5

801.8

803.0

804.5

802.7

804.6

A: LN/RAPP
STUDSVIK NUCLEAR STUDSVIK/NS-90/93 STUDVIKNUCLAR Apppendix TUDVIK/S-9/93 C.15 (25)

199 0-10-12

RIT run 269

Inside wall temperatures, Tr (K) versus axial level,z (m)

Ex~orimont

0.05

0.25

0.50

0.75

1.00

1.25

1.50

1.75

2.00

2.25

2.50

2.75

3.00

3.1

3.2

3.3

3.4

3.5

3.6

3.7

3.8

3.9

4.0

4.1

4.2

4.3

4.4

4.5

4.6

4.7

4.8

4.9

5.0

5.1

5.2

5.3

5.4

5.5

5.6

5.7

5.8

5.9

6.0

6.1

6.2

6.3

6.4

6.5

6.6

6.7

6.8

6.9

6.95

T

566.4

566.7

567 .5

565.5

565.9

565.6

565.2

565.4

565.1

565.4

567.3

567.2

567.3

564.1

564.8

565.4

563.7

562.6

564.4

564.2

562.9

*562.9

561.6

661.0

560.8

560.9

561.5

561.9

561.2

561.4

561.1

562.1

561.5

562.1

561.1

561.6

561.8

562.1

560.6

561.9

561.8

561.8

563.0

561.5

561.9

563.1

563.6

561.6

563.0

563.1

562.6

559.6

559.4

RELAP5-results

MQD3

z T

0.375 572.50

1.000 573.69

1.500 574.18

2.000 573.76

2.500 573.17

2.875 572.71

3.05 572.49

3.15 572.37

3.25 572.25

3.35 572.13

3.45 572.02

3.55 571.90

3.65 571.79

3.75 .571.68

3.85 571.56

3.95 571.46

4.05 571.35

4.15 571.24

4.25 571.12

4.35 571.00

4.45 570.88

4.55 570.77

4.65 570.66

4.75 570.55

4.85 570.45

4.95 570.35

5.05 570.25

5.15 570.15

5.25 570.05

5.35 569.96

5.45 569.87

5.55 569.78

5.65 569.70

5.75 569.61

5.85 569.53

5.95 569.45

6.05 569.38

6.15 569.30

6.25 569.23

6.35 569.16

6.45 569.10

6.55 569.03

6.65 568.97

6.75 568.91

6.85 568.85

6.925 568.80

6.975 568.77

A: LN/RAPP
STUDSVIK NUCLEAR STUDSVIK/NS-90/93 STUDVIKNUCLAR Apppendix ~tJDVIKNS-9/93 C.16 (25)

1990-10-12

RIT run 270

insiae wall temperatures, T (K) versus axial level,z (mn)

ExperimTent RELAP5-results

MOD3

z

0.05

0.25

0.50

0.75

1.00

1.25

1.50

1.75

2.00

2.25

2.50

2.75

3.00

3.1

3.2

3.3

3.4

3.5

3.6

3.7

3.8

3.9

4.0

4.1

4.2

4.3

4.4

4.5

4.6

4.7

4.8

4.9

5.0

5.1

5.2

5.3

5.4

5.5

5.6

5.7

5.8

5.9

6.0

6.1

6.2

6.3

6.4

6.5

6.6

6.7

6.8

6.9

6.95

T

566.2

567 .1

567.3

565.9

566.3

565.4

564.9

565.8

565.5

565.1

567.1

567.0

567 .1

563.9

564.6

565.1

563.5

563.0

564.2

564.0

562.6

563.3

561 .4

560.8

560.5

560.0

560.0

561.0

560.4

560.5

560.3

560.6

560.6

560.0

559.6

560. 1

559.0

559.4

559.1

559.8

559.6

568.4

735.0

768.8

786.9

798.4

808.1

816.4

822.0

825.2

828.4

830.3

824.6

z

0.375

1.000

1.500

2.000

2.500

2.875

3.05

3.15

3.25

3.35

3.45

3.55

3.65

3.75

3.85

3.95

4.05

4.15

4.25

4.35

4.45

4.55

4.65

4.75

4.85

4.95

5.05

5.15

5.25

5.35

5.45

5.55

5.65

5.75

5.85

5.95

6.05

6.15

6.25

6.35

6.45

6.55

6.65

6.75

6.85

6.925

6.975

T

573.98

575.48

575.84

575.28

574.58

574.06

573.81

573.68

573.54

573.41

573.28

573.16

573.01

572.86

572.71

572.57

572.44

572.31

572.18

572.06

571.94

571.82

571.71

571.60

571.49

571.39

571.29

571.19

571.10

571.01

570.93

570.85

570.77

570.69

570.61

570.54

570.47

570.41

570.34

570.28

570.22

570.17

570.12

570.07

570.03

569.99

569.98

MOD2

T

569.10

571 .07

573.65

575.46

574.79

574.21

573.95

573.81

573.68

573.55

573.42

573.29

573.15

573.00

572.86

572.72

572.58

572.45

572.33

572.20

572.08

571.97

571.85

571.75

571.64

571.54

571.44

571.34

571.25

571.16

571.07

570.99

570.90

570.83

570.75

570.68

570.61

570.54

570.48

570.42

570.36

570.31

570.26

570.21

570.18

570.11

570.11

NOD2 mod.

T

569.1

573 .1

573.7

575.5

574.8

574.2

574.0

573.8

573.7

573.6

573.4

573.3

573 .2

573.0

572.9

572.8

572.6

572.5

572.4

572.2

572.1

572.0

571.9

571.8

571.7

571.6

571.5

571 .4

571 .3

571.2

571.1

571.0

570.9

570.8

763.5

775.2

785.5

794.6

802.4

809.0

814.8

819.6

823.7

826.9

830.4

829.6

832.3

A: LN /RAPP
STUDSVIK NUCLEAR STUDSVIK/HS-90/93 STUDVIKNUCLAP Apppendix TUDVIK/S-9/93 C.17 (25)

1990-1 0-12

RIT run 2*72

Inside wall temtperatures. T (K) versus axial level~z (m)

Experiment

z

0.05

0.25

0.50

0.75

1.00

1.25

1.50

1.75

2.00

2.25

2 .50

2.75

3.00

3.1

3.2

3.3

3.4

3.5

3.6

3.7

3.8

3.9

4.0

4.1

4.2

4.3

4.4

4.5

4.6

4.7

4.8

4.9

5.0

5.1

5.2

5.3

5.4

5.5

5.6

5.7

5.8

5.9

6.0

6.1

6.2

6.3

6.4

6.5

6.6

6.7

6.8

6.9

6.95

T

567.6

567.8

568.1

566.1

567.0

566.1

565.0

565.9

565.6

565.3

567.9

567.8

567.2

564.0

564.7

565.2

563.0

562.5

564.3

564.7

562.7

563.3

560.8

560.2

559.9

559.5

558.8

559.2

571.1

788.1

843.7

863.7

880.3

891.9

899.6

906.9

911.7

912.1

910.8

-908.2

905.8

907 .0

901.8

901.6

899.2

899.0

897.1

895.3

892.3

890.0

B85.8

877.0

RELAPS- results

MOD3

z T

0.375 576.22

1.000 578.21

1.500 578.12

2.000 577.35

2.500 576.50

2.875 575.88

3.05 575.53

3.15 575.34

3.25 575.15

3.35 574.98

3.45 574.81

3.55 574.64

3.65 574.48

3.75 574.33

3.85 574.18

3.95 574.04

4.05 573.91

4.15 573.78

4.25 573.65

4.35 573.54

4.45 573.42

4.55 573.32

4.65 573.22

4.75 573.12

4.85 573.02

4.95 572.93

5.05 572.85

5.15 572.77

5.25 572.70

5.35 572.63

5.45 572.57

5.55 572.52

5.65 572.47

5.75 572.43

5.85 572.40

5.95 572.38

6.05 572.97

6.15 574.43

6.25 576.17

6.35 578.29

6.45 580.83

6.55 735.07

6.65 744.16

6.75 753.05

6.85 762.04

6.925 766.18

6.975 771.10

MOD2

T

571.21

574.52

578.38

577.65

576.83

576.16

575.77

575.58

575.39

575.22

575.04

574.88

574.72

574.57

574.42

574.28

574.15

574.02

573.89

573.77

573.66

573.55

573.45

573.35

573.25

573.16

573.08

573.00

572.94

572.86

572.82

572.74

776.76

790.54

803.34

815.14

825.89

835.68

844.51

852.44

859.58

866.00

871.88

877.03

882.36

882.56

886.16

MOD2 mod.

T

571.2

574 .6

578.4

577.7

576.9

576.2

575.8

575.6

575.4

575.3

575.1

574.9

574.8

574.6

574.5

574.3

574.2

574.1

573.9

573.8

573.7

833.6

850.9

865.6

877.7

887 .7

895.7

902.9

906.8

910.5

913.3

915.3

916.7

917.8

918.4

918.8

919.1

919.2

919.2

919.2

919.2

919.1

919.3

919.1

920. 1

917.8

920.0

A: LN/ RAPP
STUDSVIK NUCLEAR -STUDSVIK/NS-90/93 STUDVIK Apppendix 1JCEA~ T1JDVIKNS-9/93 C.18 (25)

1990-10-12

RIT run 275

Inside wall temPeratures, T (K) versus axial level,z (in)

Eycneriment

z

0.05

0.25

0.50

0.75

1.00

1.25

1.50

1.75

2.00

2.25

2.50

2.75

3.00

3.1

3.2

3.3

3.4

3.5

3.6

3.7

3.8

3.9

4.0

4.1

4.2

4.3

4.4

4.5

4.6

4.7

4.8

4.9

5.0

5. 1

5.2

5.3

5.4

5.5.

5.6

5.7

5.8

5.9

6.0

6.1

6.2

6.3

6.4

6.5

6.6

6.7

6.8

6.9

6.95

T

565'.2

566.1

566.3

565.0

565.3

565.1

564.6

564.8

565.2

564.8

566.8

566.6

566.8

564.2

564.9

564.8

563.2

562.7

563.8

563.7

562.3

562.9

561.1

561.1

561.5

562.6

561.0

561.3

561.3

560.8

560.6

561.0

561.0

560.9

560.6

5621.1

561.2

560.4

560.7

560.7

561.2

561.8

562.5

562.2

562.6

563.8

565.6

572.0

695.6

'728. 1

744.4

757.7

759.3

RELAP5-results

MOD3

z T

0.375 568.86

1.000 570.19

1.500 570.85

2.000- 571.03

2.500 570.97

2.875 570.77

3.05 570.67

3.15 570.61

3.25 570.55

3.35 570.49

3.45 570.43

3.55 570.37

3.65 570.31

3.75 570.26

3.85 570.20

3.95 570.14

4.05 570.09

4.15 570.04

4.25 569.99

4.35 569.94

4.45 .569.89

4.55 569.84

4.65 569.80

4.75 569.76

4.85 569.71

4.95 569.68

5.05 569.64

5.15 569.61

5.25 569.57

5.35 569.55

5.45 569.52

5.55 569.50

5.65 569.48

5.75 569.46

5.85 569.45

5.95 569.45

6.05 569.45

6.15 569.95

6.25 571.20

6.35 572.72

6.45 574.61

6.55 577.03

6.65 580.20

6.75 584.52

6.85 709.46

6.925 713.39

6.975 717.66

MOD2

T

566.87

568.57

570.53

571.06

571.02

570.83

570.71

570.65

570.59

570.53

570.47

570.42

570.36

570.30

570.25

570.19

570.14

570.09

570.04

569.99

569.95

569.90

569.86

569.82

569.78

569.74

569.70

569.67

569.64

569.61

569.59

569.57

569.55

569.54

569.53

569.53

569.53

569.54

569.56

569.58

569.63

569.68

717.65

728.47

739.28

743.64

749.00

MOD2 mod.

T

566.9

568.6

570.6

571.1

571.0

570.8

570.7

570.6

570.6

570.5

570.5

570.4

570.4

570.3

570.2

570.2

570.1

570.1

570.0

570.0

570.0

569.9

569.9

569.8

569.8

569.7

569.7

569.7

569.6

569.6

569.6

569.6

569.6

569.5

569.5

569.5.

569.5

569.5

569 .6

569.6

722.6

733.8

744.9

755.8

766.4

770.6

775.8

A: LN/RAPP
STUDSVIK NUCLEAR STUDSVIK/NS-90/93 STUDVIKNUCLAR Apppendix TUDVIK/S-9/93 C.19 (25)

1990-10-12

RIT run 315

Inside wall temperatures, T (K) versus axial level~z (m)

Experiment

z

0.05

0.25

0.50

0.75

1 .00

1.25

1.50

1.75

2.00

2.25

2.50

2.75

3.00

3.1

3.2

3.3

3.4

3.5

3.6

3.7

3.8

3.9

4.0

4.1

4.2

4.3

4.4

4.5

4.6

4.7

4.8

4.9

5.0

5.1

5.2

5.3

5.4

5.5

5.6

5.7

5.8

5.9

6.0

6.1

6.2

6.3

6.4

6.5

6.6

6.7

6.8

6.9

6.95

T

522.9

525.7

526.0

522.0

521.8

518.9

517.8

518.0

517.1

517.4

518.8

518.0

516.9

514.2

514.9

515.5

513.1

512.6

514.4

513.7

520.3

512.9

514.2

514.8

513.9

513.4

509.6

511.2

509.3

509.4

509.2

508.3

508.3

508.9

507.3

507.8

507.9

507.6

506.7

507.4

507.3

508.5

517.5

625.4

781 .0

801.3

812.9

825.7

828.9

833.5

832.3

819.2

RELAPS-results

MOD3

z T

0.375 534.00

1.000 534.50

1.500 532.79

2.000 530.60

2.500 528.41

2.875 526.92

3.05 526.27

3.15 525.92

3.25 525.58

3.35 525.25

3.45 524.92

3.55 524.61

3.65 524.30

3.75 524.00

3.85 523.71

3.95 523.42

4.05 523.13

4.15 522.84

4.25 522.56

4.35 522.28

4.45 522.00

4.55 521.72

4.65 521.45

4.75 521.17

4.85 520.90

4.95 520.63

5.05 520.36

5.15 520.09

5.25 519.83

5.35 519.56

5.45 519.29

5.55 519.02

5.65 518.75

5.75 518.49

5.85 518.22

5.95 517.95

6.05 517.68

6.15 517.41

6.25 517.13

6.35 516.86

6.45 516.58

6.55 516.30

6.65 516.03

6.75 515.74

6.85 515.46

6.925 515.24

6.975 738.79

MOD2

526.02

528.89

531.43

531.72

529.47

527.86

527.15

526.79

526.45

526.13

525.81

525.49

525.19

524.89

524.59

524.30

524 .01

523.73

523.45

523.17

522.89

522.62

522.35

522.08

521.82

521.55

521.28

521.02

520.76

520.49

520.23

519.97

519.70

519.44

519.18

518.91

518.65

518.38

518.12

517.85

517.58

517.30

517.04

516.75

516.49

516.26

516.13

MOD2 mod.

T

526. 1

529.0

531.4

531.8

529.6

528.0

527.3

526.9

526.6

526.3

526.0

525.6

525.3

525.0

524.8

524.4

524.2

523.9

523.6

523.3

523.1

522.8

522.5

522.2

522.0

521.7

521.4

521.2

520.9

520.7

520.4

520.1

519.9

519.6

519.4

872.0

879.8

883.8

885.1

884.5

-882.6

879.7

876.4

872.2

869.3

863.6

864.3
STUDSVIK NUCLEAR STUDSVIK/NS-90/93 STUDVIKNUCLAR Apppendix TUDVIK/S-9/93 C.20 (25)

1990-10-12

PIT run 317

Inside w'all temperatures, T (K) versus axial level~z (m)

Experiment

7-

0.05

0.25

0.50

0.75

1.00

1.25

1.50

1.75

2.00

2.25

2.50

2.75

3.00

3.1

3.2

3.3

3.4

3.5

3.6

3.7

3.8

3.9

4.0

4.1

4.2

4.3

4.4

4.5

4.6

4.7

4.8

4.9

5.0

5.1

5.2

5.3

5.4

5.5

5.6

5.7

5.8

5.9

6.0

6.1

6.2

6.3

6.4

6.5

6.6

6.7

6.8

6.9

6.95

T

525.4

526.9

527 .2

522.6

522.3

519.4

518.3

518.5

517.0

517.3

519.6

518.5

516.7

514.0

515.4

515.3

513.0

511.8

514.3

513.5

509.5

512.7

514.0

514.0

513.1

512.6

509.7

511.0.

509.4

508.6

509.3

507.4

508.1

552.9

761.2

857.5

863.9

886.7

897.6

897 .6

897.5

894.4

887.1

884.8

887.7

870.9

863.9

858.2

847.7

836.1

823.8

806.1

RELAP5-results

MON3

z T

0.375 538.16

3.000 538.59

1.500 536.40

2.000 533.60

2.500 531.09

2.875 529.47

3.05 528.76

3.15 528.37

3.25 528.01

3.35 527.65

3.45 527.30

3.55 526.96

3.65 526.62

3.75 526.28

3.85 525.95

3.95 525.63

4.05 525.31

4.15 524.99

4.25 524.68

4.35 524.37

4.45 524.06

4.55 523.76

4.65 523.45

4.75 523.15

4.85 522.85

4.95 522.55

5.05 522.25

5.15 521.96

5.25 521.66

5.35 521.36

5.45 521.06

5.55 520.76

5.65 520.46

5.75 520.15

5.85 519.85

5.95 519.54

6.05 519.23

6.15 518.92

6.25 518.60

6.35 518.29

6.45 517.97

6.55 517.65

6.65 517.32

6.75 517.00

6.85 516.66

6.925 516.41

6.975 748.68

MOD2

T

529.44

533.38

537.63

534.98

532.33

530.54

529.76

529.36

528.99

528.63

528.27

527.93

527.59

527.25

526.92

526.60

526.28

525.97

525.65

525.35

525.04

524.74

524.43

524.13

523.84

523.54

523.24

522.95

522.65

522.36

522.06

521.77

521.47

521.17

520.88

520.58

520.28

519.98

519.68

519.37

519.07

518.75

518.45

518.13

517.83

517.56

517.42
STUDSVIK NUCLEAR STUDSVIK/NS-90/93 STUDVIKNUCLAR Apppenaix TUDVIK/S-9/93 C.21 (25)

1990-10-12

RIT run 320

Inside wall temperatures, T (K) versus axial level~z (m)

Ex-Derirnent

2

0.05

0.25

0.50

0.75

1.00

1.25

2.50

1.75

2.00

2.25

2.50

2.75

3.00

3.1

3.2

3.3

3.4

3.5

3.6

3.7

3.8

3.9

4.0

4.1

4.2

4.3

4.4

4.5

4.6

4.7

4.8

4.9

5.0

5.1

5.2

5.3

5.4

5.5

5.6

5.7

5.8

5.9

6.0

6.)

6.2

6.3

6.4

6.5

6.6

6.7

6.8

6.9

6.95

T

523.4

524 .9

525.2

521.9

521.6

519.5

518.3

519.2

518.3

518.6

519.3

518.6

517.4

515.4

516.1

536.6

515.0

513.8

516.3

514.9

511.6

514.1

515.4

515.4

514.5

514.0

510.1

511.2

509.2

510.0

509.8

509.5

509.5

510.1

508.5

509.6

509.8

509.5

508.6

509.3

509.1

509.1

511.7

535.6

657.2

788.2

807 .1

822.3

829.3

837.3

841.7

832.3

RELAP5-resu its

MOD3

2 T

0.375 530.64

1.000 531.40

1.*500 529.88

2.000 528.00

2.500 526.27

2.875 524.94

3.05 524.37

3.15 524.07

3.25 523.77

3.35 523.49

3.45 523.21

3.55 522.93

3.65 522.67

3.75 522.40

3.85 522.15

3.95 521.89

4.05 521.65

4.15 521.41

4.25 521.17

4.35 520.94

4.45 520.71

4.55 520.48

4.65 520.25

4.75 520.02

4.85 519.80

4.95 519.58

5.05 519.35

5.15 519.13

5.25 518.91

5.35 538.69

5.45 518.47

5.55 518.25

5.65 518.04

5.75 517.82

5.85 517.60

5.95 517.38

6.05 517.16

6.15 516.94

6.25 516.72

6.35 516.50

6.45 516.28

6.55 516.05

6.65 515.83

6.75 515.61

6.85 515.39

6.925 515.22

6.975 733.64

MOD2

T

524 .77

527.92

530.67

528.86

527.08

525.65

525.02

524.71

524.41

524.12

523.84

523.57

523.30

523.03

522.78

522.52

522.27

522.03

521.79

521.55

521.31

521.08

520.85

520.62

520.40

520.18

519.95

519.73

519.51

539.30

519.08

518.87

518.65

518.44

518.22

518.01

517.80

517.59

517.37

517.16

516.95

516.73

516.53

516.31

516.11

515.92

515.83

MOD2 mod.

T

524.9

528.0

530.8

529.0

527.2

525.8

525.2

524 .8

524.5

524.2

524.0

523.7

523.4

523.2

522.9

522.6

522.4

522.2

521.9

521.7

521.4

521.2

521.0

520.8

520.5

520.3

520.1

519.9

519.6

519.4

519.2

519.0

518.8

518.6

518.4

518.1

850.1

860.0

866.3

870.0

871.7

871.9

871 .2

869.3

868.2

863.6

864 .9
STUDSVIK NUCLEAR STUDSVIK/NS-90/93 STUDVIKNUCLAR Apppendix TUDVIK/S-9/93 C.22 (25)

1990-10-12

RIT run 325

Inside wall temperatures, T (K) versus axial level~z (m)

Experiment

z

0.05

0.25

0.50

0.75

1.00

1.25

1.50

1.75

2.00

2.25

2.50

2.75

3.00

3.1

3.2

3.3

3.4

3.5

3.6

3.7

3.8

3.9

4.0

4.1

4.2

4.3

4.4

4.5

4.6

4.7

4.8

4.9

5.0

5.1

5.2

5.3

5.4

5.5

5.6

5.7

5.8

5.9

6.0

6.1

6.2

6.3

6.4

6.5

6.6

6.7

6.8

6.9

6.95

T

522.5

524.0

524.3

522.2

522.6

520.5

519.3

520.2

519.9

519.6

520.3

519.6

518.4

517.0

517.8

517.7

516.0

515.5

517.3

516.5

515.8

515.8

516.4

516.4

516.1

516.3

516.3

516.7

515.4

515.5

515.3

515.0

515.0

515.0

515.3

515.1

534.6

514.4

514.1

513.5

513.4

513.4

512.9

512.5

511.6

512.2

512.1

512.6

511.5

508.4

509.0

510.6

508.4

RELAP5-results

MOD3

z T

0.375 525.06

1.000 526.13

1.500 525.75

2.000 524.49

2.500 523.27

2.875 522.41

3.05 522.02

3.15 521.80

3.25 521.58

3.35 521.37

3.45 521.17

3.55 520.97

3.65 520.77

3.75 520.57

3.85 520.37

3.95 520.17

4.05 519.98

4.15 519.79

4.25 519.61

4.35 519.43

4.45 519.25

4.55 519.08

4.65 518.91

4.75 518.74

4.85 518.57

4.95 518.41

5.05 518.25

5.15 518.09

5.25 517.93

5.35 517.77

5.45 517.62

5.55 517.47

5.65 517.33

5.75 517.18

5.85 517.04

5.95 516.89

6.05 516.75

6.15 516.60

6.25 516.46

6.35 516.31

6.45 516.17

6.55 516.02

6.65 515.87

6.75 515.72

6.85 515.58

6.925 515.46

6.975 720.07
STUDSVIK NUCLEAR STUDSVIK/NS-90/93 STUDVIKNUCLAR Ap~ppendix TUDVIK/S-9/93 C.23 (25)

1.990-10-12

1RIT run 327

inside wall teMieratuires_, T.(K) versus axial 1evelz.z(rn)

Exnerimont RELAP5-resul ts

MQD3

z

0.05

0.25

0.50

0.75

a .00

1.25

1.50

1.75

2.00

2.25

2.50

2.75

3.00

3.1

3.2

3.3

3.4

3.5

3.6

3.7

3.8

3.9

4.0

4.3

4.2

4.3

4.4

4.5

4.6

4.7

4.8

4.9

5.0

5.3

5.2

5.3

5.4

5.5

5.6

5.7

5.8

5.9

6.0

6.1

6.2

6.3

6.4

6.5

6.6

6.7

6.8

6.9

6.95

T

524 .5

526.0

525.6

523.6

523.3

520.6

520.3

520.9

520.1

520.3

5231.1

519.7

518.5

516.5

517.2

.517.8

516.1

515.6

517.4

516.6

515.2

515.8

516.5

516.5

516.2

536.4

516.4

516.7

515.5

515.0

514.7

514.5

514.5

515.3

515.3

514.6

514.1

513.8

S13.6

511.7

510.3

509.0

512.2

576.0

754.5

790.4

809.2

826.3

834.13

838.5

846.5

853.9

847.0

z

0.375

1.000

1.500

2.000

2.500

2.875

3.05

3.15

3.25

3.35

3.45

3.55

3.65

3.75

3.85

3.95

4.05

4.35

4.25

4.35

4.45

4.55

4.65

4.75

4.85

4.95

5.05

5.15

5.25

5.35

5.45

5.55

5.65

5.75

5.85

5.95

6.05

6.15

6.25

6.35

6.45

6.55

6.65

6.75

6.85

6.925

6.975

T

527.19

528.37

527.42

525.93

524.55

523.56

523.12

522.87

522.61

522.37

522.13

521 .90

521.67

521.45

521.23

521.02

520.81

520.61

520.41

520.22

520.03

519.85

519.67

539.49

519.32

519.15

518.98

518.81

518.64

518.48

538.32

518.16

518.00

517.84

517.69

517.53

517.38

517.23

517.08

516.93

516.79

516.64

.536.50

516.36

516.22

516.11

727.74

MOD2

T

523.98

527.57

527.98

526.55

525.12

524.04

523.55

523.30

523.04

522.80

522.56

522.33

522.10

521.88

521.66

521.45

521.25

521.05

520.85

520.66

520.47

520.28

520.10

519.92

519.74

519.57

519.40

519.23

519.06

518.90

538.73

518.57

518.42

-518.26

518.11

517.95

517.80

537.65

517.51

517.36

517.22

517.07

536.93

516.78

516.66

516.52

516.48

MOD2 mod.

T

524 .1

527.7

528.1

*526.6

525.2

524 .

523.7

523.4

523.2

522.9

522.7

522.4

522.2

522.0

521.8

523.6

523.4

521.2

521.0

520.8

520.6

520.4

520.2

520.0

519.8

519.7

519.5'

539.3

519.2

519.0

518.8

518.7

518.5

518.4

518.2

518.0

834.2

847.2

857.5

865.2

870.9

875.0

878.0

879.5

881.4

878.5

880.9
STUDSVIK NUCLEAR STUDSVIK/NS-90/93 STUDVIKNUCLAR Apppendix TUDVIK/S-9/93 C.24 (25)

19 90-10-12

RIT run 331

Inside wall temperatures. T (K) versus axial level,z (mn)

Exteriment

z

0.05

0.25

0.50

0.75

1.00

1.25

1.50

1.75

2.00

2.25

2.50

2.75

3.00

3.1

3.2

3.3

3.4

3.5

3.6

3.7

3.8

3.9

4.0

4.1

4.2

4.3

4.4

4.5

4.6

4.7

4.8

4.9

5.0

5.1

5.2

5.3

5.4

5.5

5.6

5.7

5.8

5.9

6.0

6.1

6.2

6.3

6.4

6.5

6.6

6.7

6.8

6.9

6.9 5

T

519.4

520.8

520.5

517.2

515.7

514.8

514.3

514.6

514.3

513.9

519.1

517.7

518.4

516.4

515.3

514.6

512.9

511.8

511.7

511.5

510.8

512.0

513.3

512.7

511.8

511.9

511.9

512.9

511.7

511.8

511.5

511.9

511.9

511.9

512.2

512.0

512.8

513.2

512.3

512.3

512.2

512.2

512.3

513.2

512.3

513.5

514.7

512.7

514.2

513.5

513.7

510.6

510.4

RELAP5-results

MOD3

z T

0.375 520.31

1.000 521.50

1.500 521.48

2.000 521.03

2.500 520.35

2.875 519.82

3.05 519.58

3.15 519.45

3.25 519.32

3.35 519.19

3.45 519.06

3.55 518.94

3.65 518.81

3.75 518.69

3.85 518.57

3.95 518.46

4.05 518.35

4.15 518.24

4.25 518.13

4.35 518.02

4.45 517.92

4.55 517.82

4.65 517.73

4.75 517.63

4.85 517.54

4.95 517.45

5.05 517.36

5.15 517.28

5.25 517.20

5.35 517.12

5.45 517.04

5.55 516.96

5.65 516.89

5.75 516.98

5.85 517.58

5.95 518.24

6.05 518.98

6.15 519.80

6.25 520.72

6.35 521.75

6.45 522.91

6.55 524.19

6.65 525.61

6.75 527.17

6.85 529.19

6.925 530.26

6.975 711.10
STUDSVIK NUCLEAR STUDSVIK/NS-90/93 STUDVIKNUCLAR Apppendix TUDV1K/S-9/93 C.25 (25)

1990-10-12.

flIT run 332

Inside wall temperatures. T (K) versus axial level,z (in)

Experiment RELAPS-results

MOD3

z

0.05

0.25

0.50

0.75

:1.00

:1.25

1.50

1.75

2.00

2.25

2.50

2.75

3.00

3.1

3.2

3.3

3.4

3.5

3.6

3.7

3.8

3.9

4.0

4.1

4.2

4.3

4.4

4.5

4.6

4.7

4.8

4.9

5.0

5.1

5.2

5.3

5.4

5.5

5.6

5.7

5.8

5.9

6.0

6.1

6.2

6.3

6.4

6.5

6.6

6.7

6.8

6.9

6.95

T

520.1

521.6

521.3

517.4

515.9

514.3

514.5

514.1

514.5

514.1

519.2

518.5

518.6

516.6

515.5

534.7

513.1

511.3

513.1

511.7

510.3

512.2

514.1

512.8

511.9

512.1

512.1

513.1

511.8

511.3

511.7

511.4

512.1

512.7

511.7

512.2

512.3

512.7

511.8

513.1

511.1

511.1

512.4

513.3

515.0

613.4

745.7

772.7

788.4

803.6

816.3

826.6

824.6

z

0.375

1.000

1.500

2.000

2.500

2.875

3.05

3.15

3.25

3.35

3.45

3.55

3.65

3.75

3.85

3.95

4.05

4.15

4.25

4.35

4.45

4.55

4.65

4.75

4.85

4.95

5.05

5.15

5.25

5.35

5.45

5.55

5.65

5.75

5.85

5.95

6.05

6.15

6.25

6.35

6.45

6.55

6.65

6.75

6.85

6.925

6.975

T

521.30

522.66

522.59

522.04

521.24

520.66

520.40

520.26

520.12

519.98

519.84

519.71

519.58

519.46

519.34

519.22

519.11

518.99

518.89

518.78

518.68

518.58

518.49

518.40

518.31

518.22

518.14

518.43

519.20

520.06

521.04

522.15

523.40

524.82

526.41

528.20

530.24

532.57

535.26

538.44

542.23

546.87

552.72

559.80

737.31

743.21

749-42

MOD2

T

520.66

522.80

522.77

522.32

521.54

520.88

520.56

520.42

520.28

520.15

520.02

519.89

519.76

519.64

519.52

519.40

519 .29

519.18

519.07

518.97

518.87

518.77

518.68

518.59

518.50

518.42

518.34

518.26

518.19

518.12

518.06

518.00

517.94

517.90

517.85

517.82

517.79

517.77

517.76

517.77

517.78

517.83

517.87

772.15

787.13

792.44

799.47

MOD2 mod.

520.7

522.8

522.8

522.4

521.6

520.9

520.6

520.5

520.3

520.2

520.0

519.9

519.8

519.7

519.6

519.4

519.3

519.2

519.1

519.0

518.9

518.8

518.7

518.6

518.5

518.4

518.4

518.3

518.2

518.2

518.1

518.0

518.0

517.9

517.9

517.8

517.8

517.8

793.6

809.7

824.5

838.0

850.4

861.6

872.2

874.7

879.9

RIT run 136

rp

(I)

N

1000.0-

900.0 -

E

ca

800.0 -

700.0 -

-Experiment

-- RELAP5 Mod3 .. RELAP5 Mod2 miodified

RELAP5 Mod 2.5

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

-- -- -- - ---- 

H

'0

'0

0

0

L)

(D

Z)

H

600.0 -

500.0

0.0

I I- I II i I I I I I ~ 1 WT 1

0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 7.0

Axial level (in)

Inner wall temperatures for run 136

p=13.99 MPa., G=1976.6 kg per sqm-s

delta-t=10 K, heat flux=509 kw per sqm
RIT run 139

U)

H

U)

H

0

*1

1100.0-

1000.0 -

.0

E

900.0 -

800.0 -

-Exe rMen

-- R rLA'P5 MOM3 .. RELAPS Mod2 modified

-RELAPS MOM2. 5

N-)

En

z

C)

700.0-

Sflf n

(D

U.

'U .u

0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 7.0

Axial level (in)

Inner wall temperatures for run 139

P=14 .00 MPa, G=1970.5 kg per sqm-s

delta-t=9.8 K, heat flux=757 kW per sqm
c6

0

J5

.5

2

Ui)

0

4J 

14-4

0) 4J

LO> W~i4

4 w

0 E

C

5

)

$4 CI

cJi

-LO

A)

.Eu

I ": I

Co

0ý

0-

0)

C) 00

0

co0

()q) episul 'dwo) fleM

C> 0O

0l

C;
5IW

'co

ILO

(0 CDI0 N

$4 U

0 L

4J C) .

2 0 )

a: Q)

f).

c 4Qir

M 4J) c: -f i

A

Cj eq c0

Lp L-)

I -

C>~ C)-) -

(>I)~~~( apsi'IulIe
RIT run 161 PIZ

C)

1000.0 I1

900.0 -

- Experiment -- RELAPS Mod3, lbt=1.0 .. RELAPS Mod3, Ibf=0.75 --RELAP5 Mod2 modified .. RELAP5 Mod 2.5

£

0

C

EII)

800.0 -

700.0 -

'-0

C)

C0

(n

U)

C)

I0D

(D

U1

z

600.0 -

500.0-

0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5

Axial level (in)

Inner wall temperatures for run 161

P=1 3.9 9 MPa, G=503.2 kg per sqm-s

delta-t=9.5 K, heat flux'=405 kW per sqm

7.0
RIT run 221

(H

q,

Hzj

in

1000.0

900.0

~-800.0

d

E

CU700.0

600.0

500.0

H

w

0

I-i

0

H

N)

VI

tH

k)

W

:P

Id

Li

7.0

Axial level (in)

Inner wall temperatures for run 221

p=10.01 MPa, G=1973.8 kg per sqm-s

delta-t=10.1 K, heat flux=665 kW per sqm
1000.0 -RIT run 224

900.0-

-Experiment

-- RELAP5 Mod3 .. RELAP5 Mod2 modified 'A 80.0RELAP5 Mod2.5 I--~ 0) 80 .0 tI . ..... I (fl

E

cn

500.0-

0.0 .5 2. 10 3.0 15 3.5 2. 4.0 .5 .0 55 60 6. 7.

- - - - - - - - - - - - - - - - - -

Axial level (in)

Inner wall, temperatures for run224

p=10.02 MPa, G=1990.3 kg per sqm-s

delta-t=10.8 K, heat flux=860 kw per sqm
En

I-3

1000.0- RIT run 232:;

900.0-

- Experiment................

-- RrELAP5 Mod3 .. RELAPS Mod2 modiffied ,~r

ýS 800.0 -. RELAP5 Mod2.5 ------- (b

C I (fl

o) H

S700.0 1

500.0

0.. . . . . . .0 4. .'0 615 710c

Axia levl (m

Inner~~~~~~~ waltmeaue o u 3

p=1.0 MIa G=498k e£qdela-t104 K het lux758kWpers6
fliT run 238

(n

0

1000.0

900.0

~-800.0

(D

E

S700.0

600.0

500.0

kH

%D

(n

z

ID

'tj

0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 7.0

Axial level (in)

Inner wall temperatures for run 238

p=10.01 MPa, G=997.3 kg per sqm-s

delta-t=12.0 K, heat flux=556 kW per sqm
RIT run 244

I' z

~-800.0

E

W700.0

H

0

H

a

H

t.J

rn

U

0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 7.0

Axial level (in)

Inner wall temperatures for run 244

p=99.8 MPa, G=502.0 kg per sqm-s

delta-t=11.0 K, heat flux=405 kW per sqm
RIT run 259

i:i~

H

U)

z

C)

1000.0

900.0

~-800.0

S

E

(U700.0

600.0

500.0

1--j

%D

C>

C')

(n

It

k0

CD

7.0

Axial level (in)

Inner wall temperatures for run 259

p=6.9 9 MPa, G=1989.3 kg per sqm-s

delta-t=9.9 K, heat flux=870 kW per sqm
RIT run 261

z

C-)

1000.0

EH

'.0

'.0

0

H

0

H

t-3

(n4

(D3

NJa

Hý 0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 7.0

Axial level (in)

Inner wall temperatures for run 261

p=7.02 MPa, G=1998.2 kg per sqm-s

delta-t=1O.6 K, heat flux=1053 kW per sqm
1000.0-RIT run 264

900.0-

-Experiment

-- RELAP5 Mod3 .. RELAP5 Mod2 modified Hj cq.

~. 800.0 *. RELAP5 Mod2.5..........$-

I ch

E En

700.0-I

500.00

0 . .0* 0 . . . . . . . . . . . . .

Axa lee m

Ine waltmeaue oIu 6

p=.9 MIG10. k e q

det-t1. Kha e a Ix76k 
RIT run 270

In

11-3

t-I

1000.0%

900.0

*@ 700.0-

6000

700.0

0

z

:0

(D

tj.

0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 7.0

Axial level (in)

inner wall temperatures for run 270'

p=7.02 MPa, G=996.5 kg per sqm-s

delta-t=12.0 K, heat flux=660 kW per sqni
RIT run 272

'-3

0

1000.0

900.0

~-800.0

(D

E

700.0

600.0

500.0

H

~0

0

0

'-A

N,

En

(n

En

I

(D

:3'

xi

P

X

0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 -4.0 4.5 5.0 5.5 6.0 6.5 7.0

Axial level (in)

.Inner wall temperatures for run 272

p=7.02 MPa, G=999.6 kg per sqm-s

delta-t=1l.7 K, heat flux=815 kW per sqm
t'

flIT run 275

1000.0- z

900.0-

-Experflment

-- R ELAPS Mod3 .. RELAPS Mod2 modified cn

ýS 800.0- RELAPS Mod2.5 HCE

S700.0 . I -

500.0

600.0t11. Kha e q 1x40k 
flIT run 315

En

U)

1000.0.

900.0*

~.800.0.

d

E

S700.0

600.0

500.0

'I

'.0

In'-3

M)

Axial level (in)

Inner wall temperatures for run 315

p=3.01 HPa, G=1986-3 kg per sqm-s

delta-t=9.2 K, heat flux=873 kW per sqim
RIT run 317

1000.0 -

900.0-

-Experiment

-- RELAP5 Mod3 . .. RELAP5 Mod 2.5 1-3

S800.0- )t

C 0CH

EI t

EE

S700.0-

600.0-

600.0 c 0.0~~~~~ 2. ~ ~ . ~ . 0..10 . 15 40 45 50 5. . . .

Axa lee m

.............................................................. p=3.3 M~, kgper G=9873 Im.

det-t1. K, hea flx15 kW pe s
RIT run 320 1000.0

900.0

~-800.0

U)

E

700.

600.0

600.0

(I,

U,)

1-3

C:

(n~

1-4

ID

10

1,

(DA

kv

7.0 '-A

Axial level (in)

Inner wall temp eratures for run 320

p=2.99 MPa, G=1499.3 kg per sqm-s

delta-t=9.2 K, heat flux=769 kW per sqm
RIT run 327

in

U,

in

1000.0

~-800.0

V

E

0

cu700.0

I.-A En

In)

.0I

C0

0.0 0.5 1.0 1.5 2.0 2.5, 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 7.0

Axial level (in)

Inner wall temperatures for run 327

p=3.00 MPa, G=1005.6 kg per sqm-s

delta-t=9.9 K, heat flux=667 kW per sqm
RIT run 332

(n

H

t:1

4::

C)

t-4

t!I

1000.0.

900.0.

~.800.0

S

E

0

(U700.0

600.0

500.0

'0

'0

0

0

L,

I--

z

L,

It

e-),

0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 7.0

Axial level (in)

Inner wall temperatures for run 332

p=3.00 MPa, G=496.4 kg per sqm-s

delta-t=9.3 K, heat flux=464 kW per sqm

NRC FORM 335 U.S. NUCLEAR REGULATORY COMMISSION 1. REPORT NUMBER

(2491 IASugrwd bry NRC. Add Vol.. Supp.. Rev.. NRCM 1102. @Ad Addondam Numbers. If any.) 3201.*3202 BIBLIOGRAPHIC DATA SHEET

(So# instructions on the ftvesIl N UR EG!!A-0094

2. TITLE AND SUBTITLE STUDS VI K/NS-90/93

Asse .ssment of RELAP5/MOD3 Against Twenty-Five Post-Dryout 3. DATE REPORT PUBLISH.ED

Experiments Perfonmed at the Royal Institute of Technology MONTH VA

May 1 993

T. FIN OR GRANT NUMBER

____ ___ ____ ___ ____ ____ ___ ___ ____ ___ ___ ____ ___ ___ ___ L2245

5. AUTHOR (S) S. TYPE OF REPORT

Lars Nilsson Technical Report

7. PERIlOD COVER ED fincluuW eve al

8. PERFORMING ORGANIZATION - NAME AND ADDRESS Ifi NRC. pm-sids Division. Ocearwoutieon. V.1 Nuclear R ulutrry Commiwtin. n mdn addimgee. itcontraector, p'o.,j n.ie eand nimOA eddrr.I

Swedish Nuclear Power Inspectorate

6-61182 Nykoping

Sweden

an ma"~t ad*vat

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, DC 20555

10. SUPPLEMENTARY NOTES

11. ABSTRACT 1200 rapd &- teow

Assessment of RELAP5/MOD2 has been made against various experimental data, among other data from

twenty-five post-dryout experiments conducted at the Royal Institute of Technology (RIT) in Stockholm. As the

MOD3 version of RELAP5 has now been released, incorporating a different method of calculating critical heat flux

compared to RELAP5/MOD2, it seemed justified to make another assessment against the same RIT-data.

The results show that the axial dryout position is generally better predicted by the MOD3 than by the MOD2

version. T7he prediction is, however, still nonconservative, i.e. the calculated dryout position falls in most cases

downstream the actual measured point. WVhile the pre-dryout heat t 'ransfer seems to be equal for MQD2 and MOD3,

both versions giving slightly higher wall temperatures than the experiments, there is a considerable difference in the

post-dryout heat transfer. The results of the RIT data comparison indicate thai MOD3 underpredicts the post-dryout

heat trainsfer. The results of the RIT data comparison indicate that MOD3 underpre&Iicts the post-dryout wall

temperatures remarkably while MOD2 gave reasonable agreement. In this respect RELAP5MOD3 shows no

improvement over RELAP5/MOD2.

12. KEY WORDS/DESCRIPTORS ILiac ..nss wrphrams that wortwstrueeayrre,, locad"tin h ft*A0.) 13. AVAiLABILITY STATEMENT

ICAP Program U nlimited

RELAP5/MOD3 1 4. SICUR IT CLASSI FI CAT ION

Twenty-Five Post-Dryout Inf p/s ave

Royal Institute Technology Unclassified

fThis Rmoru?

Unclassified

15. NUMBER OF PAGES

16. PRICE

NFIC FORM 335 t2491