NUREG/IA-0072

-. AEEW-R2454

International

Agreement Report

LOFT Input Dataset

Reference Document for

RELAP5 Validation Studies

Prepared by

J. C. Birchley

Winfrith Technology Centre

United Kingdom Atomic Energy Authority

Dorchester, Dorset, DT2 8DH

United Kingdom

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, DC 20555

April 1992

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

agreement for the exchange of technical information., Neither

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 product 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-0072

AEEW-R2454

International

Agreement Report

LOFT' Input Dataset

Reference Document for

RELAP5 Validation Studies

Prepared by

J. C. Birchley

Winfrith Technology Centre

United Kingdom Atomic Energy Authority

Dorchester, Dorset, DT2 8DH

United Kingdom

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, DC 20555

April 1992

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 is based on work performed under the sponsorship of the

United Kingdom Atomic Energy Authority. The information in this

report has been provided to the USNRC under the terms of the

International Code Assessment and Application Program (ICAP)

between the United States and the United kingdom (Administrative

Agreement - WH 36047 between the United States Nuclear Regulatory

Commission and the United Kingdom Atomic Energy Authority Relating

to Collaboration in the Field of Modelling of Loss of Coolant

Accidents, February 1985). The United Kingdom has consented to the

publication of this report as a USNRC document in order to allow

the widest possible circulation among the reactor safety community.

Neither the United States Government nor the United Kingdom 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.
AEEW-R 2454

LOFT Input Dataset Reference Document for RELAP5 Validation Studies

J.C.Birchley

Summary

Analyses of LOFT experiment data are being carried out in order to validate the RELAP5 computer

code for future application to PWR plant analysis. The dataset used in the analyses is based on the latest available information on the LOFT facility issued by the Idaho National Engineering Laboratory

(INEL), operators of the LOFT experimental facility. The dataset was developed originally by INEL,

for use with RELAP5/MOD1, to support planning and analysis of LOFT experiments. The MODI dataset was also used by CEGB Bamwood who subsequently converted the dataset to run with MOD2.

The modifications included changes to the nodalisation to take advantage of the crossflow junction option at appropriate locations. Additional pipework representation was introduced for breaks in the intact (or active) loop. Further changes have been made by Winfrith following discussion of calculations

performed by the CEGB and Winfrith. These concern the degree of noding in the steam generator, the

fluid volume of the steam generator downcomer, and the location of the reactor vessel downcomer

bypass path.

This document describes the dataset contents relating to the volume, junction, and heat slab data for the

intact loop, reactor pressure vessel, broken loop, pressuriser, steam generator secondary, and ECC system. Also described are the control system for steady state initialisation, standard trip settings, and

boundary conditions.

NAME SIGNATURE POSITION DATE

Land Author T. C. Y(~KL. ric. U& / -: -I I

Checked ~ ~e*O4c, l 2-'1 IA._ _ _4.IJ t)(4.A~ a__ 

Approved 1 1 -C C~t- __ _ _ _ _ _ _ _ _ _

Reactor Physics Division

AEA Technology, Winfrith

January 1990

AEEW-R 2454 iii

Contents

1. Introduction ........................................................................................................................................ 1

2. LO FT Facility D escription ...... ........................................................................................................... 1

2.1. RELA P5 Input D ataset D escription ............................................................................. .. 2

2.2. Intact Loop and pump injection systems .................. 4

2.2.1. Volume related data ............................ ........ 4

2.2.2. Junction related data ....................................................................................................... 4

2.2.3. H eat slabs ........................................................................................................................ 5

2.2.4. Break Configuration for Experiments LP-SB-1 and LP-SB-2 ............... 5

2.2.5. Break Configuration for Experiment LP-SB-3 .................. 5

2.3. R eactor V essel ................................................................................................................................ 5

2.3.1. V olum e related data .......................................................................................................... 6

2.3.2. Junction related data ......................................................................................................... 6

2.3.3. H eat slabs ................................................................................................................................ 6

2.4. B roken loop ....................................................................................................................................... 7

2.4.1. V olum e related data ........................................................................................................ 7

2.4.2. Junction related data ......................................................................................................... 7

2.4.3. H eat slabs ................................................................................................................................ 8

2.4.4. Steam generator and pum p sim ulators ................................................................... 8

2.5. Pressuriser ........................................................................................................................................... 8

2.5.1. V olum e related data .......................................................................................................... 8

2.5.2. Junction related data ......................................................................................................... 9

2.5.3. H eat slabs ................................................................................................................................ 9

2.6. Steam generator secondary ....................................................................................................... 9

2.6.1. V olum e related data ........................................................................................................ 10

2.6.2. Junction related data ......................................................................................................... 11

2.6.3. H eat slabs ............................................................................................................................ 11

2.7. EC C System ................................................................................................................................ 11

2.8. Containm ent system ..................................................................................................................... 11

3. Initial and B oundary Conditions ...................................................................................................... 12

3.1. Initial conditions ............................................................................................................................ 12

3.2. Boundary Conditions ................................................................................................................ 13

3.2.1. Trip settings ........................................................................................................................ 13

3.2.2. H eat sources and sinks ................................................................................................. 14

3.2.3. M ass sources and sinks .................................................................................................. 14

AEEW-R 2454 V
4. C onclusions ....................................................................................................................................... Is

S. R eferences .... ...... ....... .................................................................................................................................. 15

AEEW-R 2454 vi
Tables

Table I a Intact loop volume data . ... ........... ~...........~...**..........*.............. 16

Table l b Intact loop junction data ............................................ ~ . 19

Table I c Intact loop heat slab dt.............. .............. ..... 22

Table 2a Reactor vessel volume data . ............................... . .......- 24

Table 2b Reactor vessel junction data . ................................... 26

Table 2c Reactor vessel heat slab dat .......... 28

Table 3a Broken loop volume data .............. . .................... 31

Table 3b Broken loop junction data ................... . .... 32

Table 3c Broken loop heat slab data .................. 33

Table 3d Broken loop volume data (for tests using SG and pump

simulators) -.......................................................................... 34

Table 3e Broken loop junction data (for tests using SG and pump

simulators) ................ ...................................................... ....... 35

Table 3f Broken loop heat slab data (for tests using SG and pump

simulators) .....-..................................... .................... .......... 36

Table 4a Pressuriser volume data ........................................................ 37

Table 4b Broken loop junction data ...................................................... 38

Table 4c Broken loop heat slab data .................................................. 39

Table 5a Steam generator secondary volume data ................................ 40

Table Sb Steam generator secondary loop junction data ..........................-.... 41

Table Sc Steam generator secondary loop heat slab data...................... 42

Table 6a ECC Systems volume data . ... ............................................. 43

Table 6b ECC Systems loop junction data .................................. .......... 44

AEEW-R 2454 Viii
Figures

Figure 1 LOFT System - intact loop ....................... 45

Figure 2 LOFT System -- broken loop .............................................. 46

Figure 3 LOFT System -- reactor vessel ............................................... 47

Figure 4 LOFT System -- pressuriser .................................................... 48

Figure 5 LOFT System -- steam generator ........................................... 49

Figure 6 LOFT System -- secondary side ............................................... 50

Figure 7 LOFT System -- ECC ...................................... 51

Figure 8 RELAP5/MOD2 Noding for LOFT Calculations 52

Figure 9 Key to noding diagrams ................... 53

Figure 10a Intact loop - description of components .............................. 54

Figure 10b Intact loop - noding of components ................................... 55

Figure 10c Intact loop - noding of heat slabs ....................................... 56

Figure 10d Intact loop - volume outlet elevations ............ . ...... 57

Figure Ila Reactor vessel - description of components ...................... 58

Figure 1 Ib Reactor vessel - noding of components .............................. 59

Figure 11c Reactor vessel - description of heat slabs ......................... 60

Figure lid Reactor vessel - numbering of heat slabs ........................ 61

Figure 1 le Reactor vessel - volume outlet elevations ......................... 62

Figure 12a Broken loop (without simulators) - description of

com ponents .......................................................................................... 63

Figure 12b Broken loop (without simulators) - noding of

com ponents ........................................................................................ 64

Figure 12c Broken loop (without simulators) - noding of

heat slabs .............................................................................................. 65

Figure 12d Broken loop (without simulators) - volume outlet

elevations .......................... 66

Figure 12e Broken loop (with simulators) - description of

com ponents .......................................................................................... 67

Figure 12f Broken loop (with simulators) - noding of

com ponents ............................................................................................ 68

Figure 12g Broken loop (with simulators) - noding of heat

slabs ......................................................................................................... 69

Figure 12h Broken loop (with simulators) - volume outlet

elevations ............................................................................................... 70

Figure 13a Pressuriser system - description of components ............. 71

Figure 13b Pressuriser system - noding of components ..................... 72

Figure 13c Pressuriser system - noding of heat slabs ........................ 73

Figure 13d Pressuriser system - volume outlet elevations ............... 74

Figure 14a Secondary system - description of components .............. 75

viii AEEW-R 2454
Figure 14b Secondary system - noding of components ....-...........- 76

Figure 14c Secondary system - noding of heat slabs .......................... 77

Figure 14d Secondary system - volume outlet elevations ............... 78

AEEW-R 2454 ix
Acknowledgments

The author wishes to acknowledge the value of discussions with staff from the Central Electricity Generating Board (CEGB), Barnwood. A number of the figures used in the report are taken from Reference 3 (NUREG/CR-0247). The work was financed by the CEGB under the Thermal Reactor Agreement

AEEW-R 2454 x
LOFT Input Dataset Reference Document

for RELAP5 Validation Studies

1. Introduction

The RELAP5 computer code (Ref 1) has been chosen for independent assessment of small break

LOCA and intact primary circuit faults for the Sizewell 'B' PWR. To provide confidence in RELAP5

as a suitable tool for this assessment, a series of validation studies is being carried out, via analyses of

experimental data from rigs, from plant commissioning tests, and from unplanned plant transients that

have occurred in the past. The cases being analysed have been chosen on the basis of the provision of

data which address the important macroscopic phenomena that are likely to occur in those transients

within the Sizewell 'B' design basis envelope, and are identified in Reference 2. The main sources of

such data are the LOFT and LOBI integral test facilities.

This report describes the LOFT input dataset, based on the latest available information on the LOFT

facility (Ref 3). The dataset used in the U.K. calculations is based on the input deck developed by

INEL, and described in Reference 4. Section 2 of this report provides a brief description of the LOFT

facility. Section 3 provides a detailed description of the dataset.

The LOFT experiments that have been/are being/will be analysed are:

" L9-1 Loss-of-feedwater with recovery via: (i) primary PORV; (ii) steam generator heat sink.

" L9-3 Loss-of-feedwater anticipated transient without trip (ATWT).

" L9-4 Loss of on and offsite power ATWT.

" LP-FW-1 Loss of main and auxiliary feedwater with recovery via primary feed and bleed.

" L3-5 Small (4 inch equivalent) cold leg break - pumps off

" L3-6 Small (4 inch equivalent) cold leg break - pumps on

" L5-1 Intermediate (10 inch equivalent) cold leg break - pumps on

" LP-SB-l Small (3 inch equivalent) hot leg break - pumps off

" LP-SB-2 Small (3 inch equivalent) hot leg break - pumps on

" LP-SB-3 Small (2 inch equivalent) cold leg break - w/o HHSI, delayed pump trip

2. LOFT Facility Description

The LOFT facility was designed to model the nuclear and thermal-hydraulic phenomena which would

take place in a loss-of-coolant accident (LOCA). The scaling philosophy adopted was to reduce the

coolant volumes and flow areas for the components by the ratio of the LOFT core power (50 MW(th))

to that of a typical four-loop commercial PWR (3400 MW(th)). This was not completely achieved,

however, with the result that some of the components were oversized. In addition, the vertical scaling

was not preserved with several components considerably shorter than their commercial PWR counterparts. Despite these shortcomings, the components in LOFT were functionally similar to those of a

commercial PWR, and the transient simulations carried out in LOFT (Ref 3, for example), exhibited

most of the phenomena that may be expected in a PWR LOCA or an intact primary circuit fault transient. In particular LOFT was at least an order of magnitude larger than most other integral facilities,

AEEW-R 2454 4-1
and was unique among them in containing a nuclear core.

The main features of LOFT are summarised as follows:

i. A reactor vessel with an annular downcomer, a lower plenum, an upper plenum, and a nuclear

core with lower and upper support structure.

ii. An intact (active) loop with an active steam generator, pressuriser, and two primary coolant

pumps connected in parallel.

iii. A broken (test) loop containing pipework with resistance and elevation changes designed to

simulate the steam generator and pump resistance, and two quick acting blowdown valve assemblies. (The steam generator and pump simulators were disconnected in several of the intact primary circuit fault transient experiments.)

Despite the terminology "intact/broken loop", the majority of the small break LOCA experiments

in LOFT were conducted with the break in the active loop.

iv. A blowdown suppression system consisting of a header, suppression tank and a spray system, to

simulate the containment response to a LOCA.

v. An emergency core coolant (ECC) injection system consisting of two low head safety injection

(LHSI) pumps, two high head safety injection (HHSI) pumps, and two accumulators, and the associated pipework.

The LOFT facility is depicted in Figures 1 through 7. Figures I and 2 show the primary coolant system (PCS); figures 3 through 5 show cutaways of the reactor vessel, the pressuriser, and the steam

generator, figure 6 shows the secondary system, and figure 7 the ECC system.

2.1. RELAP5 Input Dataset Description

The input dataset described in the present document is based on the model developed by INEL for analyses of LOFT intact circuit fault and LOCA experiments using RELAPS/MODI (Ref 4). The MOD1

dataset was used by CEGB Bamwood for analysis of LOFT small break experiment LP-SB-3 (Ref 5),

and was subsequently modified for further analyses of LOFT experiments LP-SB-3 (Ref 6), LP-SB-1

(Ref 7), LP-SB-2 (Ref 8), LP-FW-1 (Ref 9), and L9-4 (Ref 10), using MOD2. The version used for

analysis of experiment LP-SB-2 constitutes the major part of the present model.

Modifications made by Barnwood are described in the above references but have not been formally documented. The input datasets are, however, archived. The modifications from the original dataset are

essentially of four types:

i. Renoding of the reactor vessel in order to make use of the cross-flow junction option in MOD2.

This enabled simplification of the noding for the connections between the loops and the reactor

vessel. In particular, the intact and broken loop cold legs are connected to only a single fluid

cell.

ii. Adjustments to provide closer representation of the hardware. This concerned, in particularly,

the reactor vessel downcomer bypass flow paths (following discussion of sensitivity studies performed by Barnwood) and steam generator downcomer flow area. There is also supporting information information from INEL for these changes (referenced below).

iii. Subdivision of the lowest node in the steam generator boiler and tubes to provide better resolution of the fluid distribution during boildown of the steam generator in loss-of-feed transients.

AEEW-R 2454 -2-
iv. Inclusion of the intact loop hot leg and cold leg break geometry, ECCS, and broken loop SG and

pump simulators (to be commented out when not applicable).

The RELAP5 input dataset for the LOFT facility consists of seven parts:

i. Intact loop components (100-199, 900-999)

ii. Reactor vessel components (200-299)

iii. Broken loop components (300-399)

iv. Pressuriser components (400-499)

v. Secondary coolant system components (500-599).

vi. ECC system components (600-699).

vii. Containment volume components (800-899)

Also represented are the internal heat structures in the reactor vessel and vessel wall, the pipework of

the primary coolant system and the pressuriser, the conductors between the primary and secondary

sides, and the secondary side shell.

During the course of the USNRC and OECD LOFT experiment programmes, the facility was

configured in several different ways, to represent breaks of different size or location, etc. Certain sections of pipework were added or valved in or out accordingly. In any particular experiment only part

of the whole configuration was used. In the interest of compactness, all of the configuration relevant

to the validation of RELAP5 is represented in a single reference dataset. For calculation of any particular experiment, the representation for LOFT hardware that was not used is commented out.

Because the model is used for a range of transients compromises are made between economy of calculation and detail of representation. The degree of detail allows realistic simulation of small breaks (in

which it is necessary to be able to track the level in the primary system and the reactor vessel), and

transients such as loss of feedwater (where it is necessary to track the level in the steam generator).

When the model was developed it was expected that similar noding would be used for all the transients, rather than seek run time economies by using different noding for different classes of transient.

In making subsequent modifications involving the addition of further detail, the new model became,

essentially, a new base deck. For example, the noding in the intact loop hot leg and cold leg was

modified to include small BRANCH components at the locations of the connection to the break lines.

The use of a small fluid volume at the break connection is recommended by INEL, although Bamwood

had reported that the results were not significantly affected by the noding change. The new noding is

retained for simplicity and to reduce the amount of input model maintenance, documentation, etc. In

general, however, the size of the hydrodynamic volumes are specified such that all volumes have comparable flow length, within the constraints implied by the likely level of detail required. One of the

values of length, flow area, and volume is always set to zero, so that this value is calculated by the

code. If the hydraulic diameter is input as 0.0, then it also is calculated by the code, from the flow

area.

The from/to volume number has the format - XXXNNMM - where XXX is the component number,

NN is the volume number within the component, and MM = 00 for inlet, 01 for outlet. If the area for

a junction is set to zero in the input deck, the smaller flow area of the adjacent volumes is used.

Figure 8 shows the nodalisation scheme used in the input dataset.

AEEW-R 2454 -3-
2.2. Intact Loop and pump injection systems

The connections of the intact loop to the reactor vessel and to the pressuriser surge line are included

here. Also included in the description of the intact loop pipework are the primary coolant pump injection, and the break pipework from the intact loop.

2.2.1. Volume related data

The intact loop components, including the two primary coolant pumps and the primary side of the

steam generator are identified in figure 10a,b,c, and the volume outlet elevations, in figure 10d. Table

la describes the noding and details of the components. The pump inlet and outlet regions, the ECC

connection, and the connection between the lot leg and pressuriser surge line are simulated as tees. A

PIPE component comprising 10 fluid volumes is used to represent the steam generator tubes, with the

lowermost section noded more finely than the remainder. Components 100, 105, 110, and 112

represent the hot leg, 114 and 116 the steam generator inlet and outlet plena, respectively, and 118 the

crossover leg. A BRANCH component 120 simulates the tee at which the pipework divides to form

the two parallel paths for the pumps. Pump number one is represented by components 125 and 130

for the pump suction and entry, 135 for the pump, and 140 and 145 for the outlet and discharge.

Pump number two is represented in similar manner by components 155 and 160 (suction and entry),

the PUMP component 165, and 170. A second BRANCH simulates the confluence of the pump

discharges. Components 175, 180, 184 and 185 represent the cold leg.

2.2.2. Junction related data

Table 10b details the junction data for the intact loop. The two junctions at the pump suction tee which

connect component 120 with 125 and 155 have half the flow area of component 170. Connection to

the pressuriser spray line is represented by a junction from BRANCH component 150. The ECC connects to BRANCH component 185. Junctions 11401 and 11602 have smaller flow areas than the

minimum flow area of the flow areas of the adjacent volumes, and are specified with the abrupt area

change option, thus simulating the orifices installed in the steam generator inlet and outlet plena. The

loss coefficients are adjusted to produce the correct pressure drop as specified in the LOFT System and

Test Description (Ref. 3).

The LOFT configuration contains a number of pathways by which fluid can pass between the inlet and

outlet nozzles without passing through the main flow paths within the reactor vessel. Some of these

paths are lumped together in the RELAPS input dataset in the form of a single pathway from the

vessel inlet to the outlet, (sometimes referred to as the downcomer bypass).

Analyses have shown that the transient conditions, particularly following a small break LOCA, are sensitive not only to the size of the downcomer bypass but also to the elevation. In earlier versions of the

input model, the downcomer bypass was represented as a path within the vessel itself, between the top

of the inlet annulus and the top of the upper plenum, SNGLJUN component 208. Vessel bypass data

given in Reference 11 indicate that the bulk of the downcomer bypass is at the elevation of the inlet

and outlet nozzles, and that the pathway represented by junction 208 admits only a small fraction of

the downcomer bypass flow. This is supported by sensitivity studies carried out in the analysis of experiment LP-SB-1 (Reference 11). The input lines for junction 208 are retained, for reference, as comments in the present input deck.

AEEW-R 2454 4-
The downcomer bypass is represented by a junction from volume 185 to 100, with the flow area set to

the cold leg area. The bypass flow rate is kept at 2.4 percent of the total loop flow. The form loss

coefficient, determined from pressure drop considerations, is set to 7200.

The tee junctions for the pump inlet and outlet regions are specified as normal (i.e. not cross-flow)

junctions. The ECC connection tee is simulated as a normal junction. The connections between the

reactor vessel upper plenum and intact loop hot leg, and between the inlet annulus and cold leg are

modelled using cross-flow junctions, with the vessel fluid volumes (and not the pipe volumes) specified

as cross-flow. The cold leg also connect to the reactor vessel filler gap via a normal junction. The

connection between the intact loop hot leg and pressuriser surge line is specified as a cross-flow junction, with the hot leg volume as cross-flow, and the modified entrainment model invoked.

The primary coolant pump injection is via TMDPJUN components 900 and 901, the coolant conditions

defined by TMDPVOL components TMDPVOLs 910 and 911.

2.23. Heat slabs

Heat slabs are included for the steam generator tube walls and all the intact loop pipework, except the

ECC line and the pump housing. The heat slab data are given in table Ic.

2.2.4. Break Configuration for Experiments LP-SB-1 and LP-SB-2

For hot leg break experiments LP-SB-1, SB-2 the noding for the intact loop hot leg is modified. A

section of the hot leg, SNGLVOL component 104, is introduced in between 100 and 105. A crossflow

SNGUUN then connects component 104 to the SNGLVOL component 102 that represents the break

line. The piping for the break line from the intact loop hot leg is represented by SNGLVOL component 102. The break itself is represented by the VALVE component 103. The lines of input

corresponding to the hot leg break geometry are appended to the intact loop representation, and are

commented out for experiments other than LP-SB-1 and SB-2. Multipliers of 0.93 and 0.81 are used

for single and two phase break flows, respectively. However, multipliers of up to 1.2 had been used in

some sensitivity studies carried out by Barnwood.

22-5. Break Configuration for Experiment LP-SB-3

For cold leg break experiment LP-SB-3 the a section of pipework is added to represent the break line

and orifice. The break piping is represented by BRANCH components 181 and 182, the break orifice

represented by VALVE component 183. Component 181 is connected to cold leg volume 184 by

means of a cross flow junction. The lines of input corresponding to the cold leg break geometry are

appended to the intact loop representation, and are commented out for experiments other than LP-SB-3.

Multipliers of 0.93 and 0.81 are used for single and two phase break flows, respectively.

2.3. Reactor Vessel

The reactor vessel input data are based on Reference 1. Because of the complicated geometry of the

reactor vessel, particularly in and around the core, simplifications have been made to represent the

vessel with a degree of detail consistent with the remainder of the system.

AEEW-R 2454 -5-
23.1. Volume related data

Thie components representing the reactor vessel are identified in figure la,b,c,d, and the elevations of

the volumes indicated in figure I le. The volume data for the reactor vessel are described in table 2a.

Components 200, 202, and 205 simulate the inlet annulus. The downcomer and vessel filler gap are

represented by ANNULUS components 210 and 223, respectively. Components 215 and 220 simulate

the lower plenum and lower head. The volume containing the lower core support structure and flow

diffuser plate is represented by component 225. Components 230 and 235 simulate the core and core

bypass, respectively. Finer noding is used for the core than for most of the vessel, in order to provide

sufficient resolution of the core fluid distribution during small break LOCAs in which core uncovery

occurred. Component 240 represents the region containing the upper end boxes and the lower part of

the upper core support structure. Component 245 represents the cross-flow region up to the level of

the control rod guide structure. Components 250 and 251 simulate the upper flow skirt region and the

dead end region of the fuel modules up to the level of the control rod drive housing, respectively.

Components 252, 255, and 260 simulate, respectively, the upper plenum at the connection with the intact and broken loop hot legs, the lower part of the upper plenum above the level of the hot leg connections, and the dead end region at the top of the upper plenum. All the volumes are vertically

oriented.

2.32. Junction related data

The geometric data for the junction related components in the reactor vessel are shown in table 2b.

All the junctions within the vessel model are oriented vertically, and all BRANCHes in the vessel are

one-dimensional. The connections between the inlet annulus and the intact and broken loop cold legs,

and the upper plenum to the intact and broken loop hot legs are simulated using horizontal junctions,

with the respective vessel components defined as cross-flow volumes for those junctions.

As stated in Section 2.1, the downcomer bypass is represented by a connection from the vessel inlet

nozzle to outlet nozzle. However, the original path, junction 208, is retained for reference but is commented out in the present input deck. The junction areas in the core bypass volume, between the

lower core support volume and upper end box/support volume, are specified to give approximately five

percent flow. Details of the bypass path flow are given in Reference 11.

The pressure drop distribution in the vessel is not known in detail with accuracy. The additional loss

coefficients in the reactor vessel are chosen to provide the correct total pressure drop across the vessel.

2.33. Heat slabs

The heat slab components in the vessel are shown in figure 1 lc. The following heat structures are

used, as shown in figure lId:

i. Vessel wall

ii. Vessel bottom

iii. Vessel filler blocks

iv. Core support barrel

v. Core lower support structure

AEEW-R 2454 -6-
vi. Flow skirt - core filler assembly

vii. Active core

viii. Upper core support structure

ix. Internals in upper plenum

x. Top plate

Two-sided heat structures are used to represent the vessel walls, bottom, top plate, and the upper sections of the fuel modules. The fuel rods, filler assemblies, support structures, flow skirt, and internals

are modelled using one-sided heat structures. A detailed description of the geometric data for the heat

structures is given in table 2c.

2.4. Broken loop

Figure 12ab,c displays the broken loop geometric data, and figure 12d shows the volume outlet elevations. The broken loop. loop pipework is represented up to the isolation valves, with the steam generator and pump simulators not included since these sections were not used in the experiments

analysed here The Reflood Assist Bypass System (RABS) consisted of an assembly comprising two

parallel lines, each one valved (normally closed but admitting some flow through leakage). The lines

connected at each end, via a tee, to a section of pipe. The pipe sections connected to the broken loop,

one to the hot leg and one to the cold leg. To allow room for the RABS assembly, the pipe from the

cold leg was elevated above the loop elevation, and connected vertically to the top of the cold leg pipe

and horizontally to the hot leg.

2.4.1. Volume related data

PIPE component 350 represents the line to the cold leg break plane. PIPE component 315 represents

the line to the hot leg break plane, and which comprises the steam generator and pump simulators.

The dataset contains two sets of input lines, one set to be commented out depending on whether the

simulators were used or not. For experiments in which the simulators were not used, fluid cells 315-3

through 315-12 are, in effect, commented out and the length of cell 315-2 increased to accommodate

the additional length of straight pipe.

The RABS is simulated by two PIPE components (370 and 380). These are connected to BRANCH

components 310 and 345 representing the broken loop hot leg and cold leg reducer sections. The line

from the cold leg is at an elevation of 0.64 m.

The geometric data for the volumes are detailed in table 3a.

2.4.2. Junction related data

Table 3b describes the input data for the junctions in the broken loop. The loss coefficients are

specified to give the correct pressure drop distribution. The junctions in the broken loop are normal,

one-dimensional, and oriented horizontally with the exception of the RABS connections. The connection to the broken loop cold leg is oriented vertically and normal (i.e. not crossflow), while the hot leg

connection is horizontal and crossflow. The PIPE sections of the RABS in the broken loop are connected to each other via a SNGLJUN (375) whose loss coefficients are specified so as to yield a flow

AEEW-R 2454 -7-
of 1.4 percent of the full steady state flow. This represents the average flow through the (leaking)

valve in the RABS, derived from steady state measurements of loop flow and temperature. The size of

the bypass flow through the RABS, like the downcomer bypass, can have a significant effect on the

thermal-hydraulic response in some transients. Unfortunately, the RABS flow is not known with certainty and, moreover, is believed to vary from experiment to experiment depending on how securely

the valve reseats after it had been opened. (The RABS was normally tested before experiments were

conducted). The flow resistance may be varied in some experiment simulations.

2.43. Heat slabs

The input data for the broken loop configuration includes heat slabs for the pipework for the broken

loop hot and cold legs and RABS. The heat slab data are given in table 3c. The remarks pertaining to

the whether the simulators were used apIlies to the heat slabs, also.

2.4.4. Steam generator and pump simulators

The LOFT configuration includes a section of pipework designed to simulate the flow path from the

broken loop hot leg to to cold leg break. The pipework includes the steam generator and pump simulators, which present flow resistances representative of large break LOCA reflood conditions, and

elevation changes similar to those in the intact loop pipework. For several of the experiments, the

simulators were moved aside and were replaced by a straight length of pipe leading to the break plane.

The pipework is represented by PIPE component 315, containing 12 fluid cells. Large loss coefficients

are input to represent the flow resistance provided by orifice plates in the steam generator and pump

sections of the pipe. The volume, junction and heat slab data are given in tables 3d, 3e, and 3f,

respectively. Figure 12e displays the volumes and figure 12f the volume outlet elevations for the

steam generator and pump simulators.

2.5. Pressuriser

The input data for the pressuriser are based on reference 1. The pressuriser is modelled in some detail

in order to simulate the response to in- and out- surges and to flows through an open relief valve. The

representation comprises 13 fluid volumes, 16 junctions, and 9 heat slabs.

2.5.1. Volume related data

Figure 13ab,c identifies the components of the pressuriser, and figure 13d shows the volume outlet

elevations. This part of the system includes the pressuriser surge line, which is represented by a

SNGLVOL and a PIPE component (components 400 and 405, respectively) comprising three fluid

volumes overall. The pressuriser tank is simulated using a PIPE component (415) consisting of seven

fluid volumes. A BRANCH component (440) is used to represent the spray line, connected to the top

of the pressuriser tank via a VALVE (445), and to the intact loop cold leg. The volume related data

are given in table 4a.

AEEW-R 2454 -8-
2.52. Junction related data

Table 4b shows the junction related input data for the pressuriser. Component 410 is a SNGLJUN

simulating the entry to the pressuriser. Component 420 is a BRANCH used to connect to three

VALVE components which represent the Pilot Operated Relief Valve (PORV) (455), the Safety Relief

Valve (SRV) (450), and a dummy valve used to control the pressure for the steady state. The areas of

the PORV and SRV are specified to provide the correct relief flows. The spray line flow resistance is

set to give the specified spray flow rate. The PORV, SRV and spray valves are represented by trip

valves in the input model.

25.3. Heat slabs

The walls of the pressuriser are represented by heat structures, but the surge line does not have any

heat structure representation. The pressuriser heaters were not used in those experiments being

analysed and are not simulated in the input data. The heat slab data are given in table 4c.

2.6. Steam generator secondary

Data for the configuration of the steam generator secondary are not available in same degree of detail

for for the rest of the system. Limited data are provided in reference 1, and some additional data are

given in reference 10.

Unfortunately, there is no value given for the diameter of the boiler shroud. The original dataset assumes a value 1.289 m for the internal radius, which is used to calculate the boiler and downcomer

flow areas and volumes. This value implies a distance of 0.035 m between the outermost tubes and the

shroud, which is comparatively large compared with the tube pitch (0.0191 m). The dimensions used

in the RELAP5 dataset have consistently resulted in an underestimate of the initial inventory by about

100 kg. A revised calculation of experiment L9-3 used a larger downcomer area corresponding to the

internal diameter of the shroud set to 1.219 m, the diameter of the tube bundle. This gave better

agreement for the estimated initial inventory but distorted the physical picture because the shroud

would not, of course, have been in contact with the tubes.

In order to overcome the discrepancy in mass inventory, the following modification is made to the input dataset. A reduction in the shroud diameter to 1.2572 m is assumed which corresponds to a distance of 0.0191 m between the outermost tubes and the shroud inner wall, i.e. the same as the tube

pitch. This value results in an increase in the downcomer area to 0.297 m2, and a reduction in the

boiler flow area to 0.258 m2. The net effect is that the total volume in steam generator is not

significantly changed, but during power operation (when the fluid in the boiler is two-phase), the liquid

inventory, as calculated by RELAP5/MOD2, is increased by about 60 kg. This results in an inventory

close to the quoted value at full power. It should be notedhowever, that the inventory calculated by

RELAP5/MOD2 depends also on the code models for interphase drag and subcooled void, and the

flow resistance in the input dataset.

The data in reference 10, and the assumed and derived values for dimensions are summarised below.

AEEW-R 2454 -9-
Characteristic Value Units

Tube bundle diameter 1.219 1m1

Outside diameter of tubes 0.0127 in

Number of tubes 1845

Tube pitch (from above) 0.0191 M.

Assumed shroud inner diameter (based on tube pitch) 1.2572 m

Thickness of boiler shroud (from original dataset) 0.0127 m

Shroud extermal diameter = downcomer inner diameter 1.2826 in

External diameter of secondary shell 1.528 in

Thickness of secondary shell (from original dataset) 0.0528 in

Outer diameter of downcomer annulus (from above) 1.4224 In

Flow area of downcomer (from above) 0.2970 m2

Assumed shroud inner diameter (based on tube pitch) 1.2572 in

Area inside shroud (from above) 1.2414 m2

Outside diameter of tubes 0.0127 m

Number of tubes 1845

Area occupied by tubes (from above) 0.4674 m2

Flow area of bundle in horizontal plane (from above) 0.7740 m2

Flow area in dataset (taking into account flow direction) 0.2580 m2

Mass inventory at full power 2041 kg

The steam generator secondary system, including the feedwater system and the components downstream of the MSCV are simulated by means of 21 fluid volumes, 21 junctions, and 15 heat slabs.

2.6.1. Volume related data

Figure 14ab,c identifies the components in the steam generator secondary, and figure 14d indicates the

volume outlet elevations. The steam generator secondary The volume data for the secondary coolant

system are detailed in table 5a.

The boiler is represented by the PIPE component 515. The length of the flow path from volume 515-

01 to 515-05 is greater than the elevation change because the fluid has to flow around the baffles inserted in the boiler. Smaller nodes are employed in the lower part of the boiler and downcomer (510),

to make it possible to track the level in those volumes as the steam generator boils down following a

loss of feedwater. The downcomer is simulated using the annulus component (510).

The separator is represented using the SEPARATR component 500. The quantity VOVER, the liquid

fraction above which liquid carryover occurs, has the value 0.2. Carryunder occurs at a liquid fraction

less than VUNDER, which has the value 0.0002. A small value was used for VUNDER in order to

suppress the instability when steam is transported into the downcomer while there is still significant

liquid present.

Liquid is returned from the separator to the region simulated by the SNGLVOL 505, and hence to the

upper downcomer, represented by BRANCH component 508, where it mixes with the subcooled feedwater. The separator bypass is simulated by a SNGLVOL 502, which connects to the separator liquid

return and to the lower part of the steam dome (520). The lower, and upper (525) parts of the steam

AEEW-R 2454 -10-
dome are simulated using SNGLVOL components.

The steam main system is represented by a SNGLVOL components 530 and 541 for the sections of

pipe before and after the steam control valve. The condenser and and volume connected to the steam

bypass are simulated using the TMDPVOL components 542 and 546. steam dome are simulated using

SNGLVOL components.

2.62. Junction related data

The junction related input data are shown in table 5b. The initial circulation rate and flow resistance in

the steam generator are not known accurately. The loss coefficients have a bearing on the circulation

ratio which, in turn, affects the inventory during steady state operation. Prior to increasing the downcomer area, sensitivity studies were performed in which the flow resistances were reduced in attempt to

raise the circulation ratio and inventory. However, the inventory could not be increased satisfactorily

via any plausible reductions, and the loss coefficients were reset to their original values.

The feedwater valve is simulated using the TMDPJUN 566. The steam flow control valve and steam

bypass valve are simulated using VALVE components 540 and 545, respectively. The steam flow control valve, when closed, admits a small but noticeable leakage which is slightly different each time the

valve closes. The leakage flow is generally in the range 0.05 to 0.1 kg/s.

2.63. Heat slabs

The heat slab input data for the steam generator are given in table 5c. The heat slabs represent the

steam generator shell, and the shroud separating the downcomer and boiler regions. The steam generator tube walls are included in the description of the steam generator primary side.

2.7. ECC System

A SNGLVOL (605) is used to represent the ECC header, to which are connected the accumulator line,

component 615, and the borated water storage tank (BWST). TMDPVOL components 625 and 620

represent the BWST and accumulator, respectively. The connection between the ECCS header and the

intact loop cold leg (185) is via VALVE component 600. A second VALVE (610) connects the

header with the accumulator pipe. The low and high head ECC pumps are represented by TMDPJUN

components 630 and 640, respectively. The configuration is shown in figure 10, the volume and junction data are given in table 6ab. The HHSI and LHSI flow rates are specified separately for each experiment. No heat structures are used in the input for the ECCS.

2.8. Containment system

The containment (or, strictly, the blowdown suppression tank) is represented by time dependent

volumes 805, 810, 815, 820, and 825 which define the conditions downstream of the pressuriser

PORV, SRV, intact loop hot leg break, intact loop cold leg break, and broken loop cold leg break,

respectively. Only those components relevant to each experiment are used, the remainder are commented out.

AEEW-R 2454 -I]-
3. Initial and Boundary Conditions

Some of quantities which define the initial and boundary conditions (e.g. the steam bypass valve setpoints) can be considered as having standard values. In general, however the initial and boundary conditions vary from test to test.

The initial and boundary conditions are specified via the trip and control systems, and table data. For

the initial conditions of a particular run, the primary system pressure, the primary loop mass flow rate,

the core power, the secondary side downcomer level are set in the input deck to their required values.

The initial state is achieved by means of a pseudo-steady state calculation in which those quantities

(e.g. loop flow rate) which cannot be specified explicitly are achieved via the control system's action

on some other quantity, in this case the pump speed. The boundary conditions for the transient calculation ame specified directly.

3.1. Initial conditions

The initial primary system pressure is specified by means of a time dependent volume attached to the

pressuriser. This volume controls the system pressure directly and is removed in transient calculation.

In reality pressuriser sprays and heaters are deployed in the LOFT pressuriser, but these are not invoked in steady state calculations.

The initial core power is set to the measured or specified value, in the relevant heat structure card.

The mass flow rate is controlled via the pump speed, which is continually adjusted using a

proportional-integral controller on the difference between the current flow rate and the required flow

rate. This readily drives the flow rate to the required value, thus:

(o. = roost - 0.2 (in - mI,,,qd ) - 0.1 f (in mreeqd - )dt,

where the mass flow is evaluated at junction 18001 in the intact loop cold leg.

The steam generator pressure is controlled via the main steam control valve whose position, X, is adjusted using a proportional-integral controller on the steam line pressure, p, thus:

X = 10V (p -prtqd ) + 5.10-10 f (P -Prqi )dt

X = 0.9 + idt.

The steam generator downcomer level is controlled via the feedwater flow which is itself controlled on

the level and the steam flow, thus:

rAfnd = Au. - 20.0 (level - level,,qd)

Although the steam generator inventory is actually monitored via the level in the downcomer, there is

some uncertainty over the relation between level and inventory. In particular, RELAP5/MOD2 tends

to underpredict the inventory as a function of the level in steady state conditions. An overestimate of

the level might be used in order to specify the initial inventory more accurately.

AEEW-R 2454 -12-
3.2. Boundary Conditions

The controllers for the initial conditions are disabled at the start of a transient calculation, and the trip

and control logical, and the table data for the transient then become effective.

32.1. Trip settings

The trip logic used in LOFT experiments varies considerably from test to test, and a standard set of

trips does not exist. However, certain of the trips are characteristic of the LOFT facility and are essentially test independent and may be considered as standard. However, although their operation is generally test independent, the setpoint values vary from test to test. The trip conditions in the reference

dataset are:

i. Pumped ECC and accumulator -

(hot leg pressure)

HHSI on: 8.07 MPa

LHSI on: 1.03 MPa

Accum on: 4.14 MPa

ii. Pressuriser spray (except loss of offsite power) -

(hot leg pressure)

On: 15.32 MPa

Off: 15.16 MPa

The spray valve is modelled as a trip valve.

iii. Pressuriser PORV opening and closing (except loss of offsite power) -

(hot leg pressure)

Open: 16.20 MPa

Close: 16.00 MPa

The PORV is modelled as a trip valve.

iv. Pressuriser SRV opening and closing

(hot leg pressure)

Open: 17.24 MPa

Close: 16.46 MPa

The SRV is modelled as a trip valve.

v. Main steam control valve (when enabled)

(steam line pressure)

Open: 7.12 MPa

Stop opening: 6.98 MPa

Close: 6.50 MPa

Stop closing: 6.57 MPa

The control valve rate of opening/closing is 0.06/s.

vi. Steam bypass opening and closing (when MSCV disabled)

(steam line pressure)

Open: 6.50 MPa

Close: 6.35 MPa

The bypass valve rate of opening/closing is 0.143/s.

vii. Auxfeed on and off (following SI signal)

(SG level)

AEEW-R 2454 -13-
On: 2.1844 m

Off: 2.9464 m

viii. Scram, termination of main feed, and MSCV closure on SI signal

(hot leg pressure)

Active: 14.28 MPa

The remaining trip logic and settings are experiment specific, indeed define the experiment. Such trips

include break opening, scram, termination of main feed other than on SI signal, pump trip.

32.2. Heat sources and sinks

The heat input from the nuclear fuel is specified, during steady state, as a constant power. For transients involving scram, a decay heat table is generally specified based on tabulated data provided by

INEL. For transients not involving scram, the power is calculated either by input of a supplied table

for power against time, or by means of the point kinetics model in RELAP5/MOD2. Reactivity

parameters, derived by INEL from physics calculations performed as part of the planning and safety

analysis for LOFT ATWT sequences, are included in the input deck. The treatment of power generation using the kinetics model is described in Reference 13. The input lines for the reactivity model are

commented out if the kinetics model is not used. The dimensions and enrichment of the LOFT core

are different from that of a commercial PWR, with the result that the reactivity feedback roughly simulates a PWR core at the end of life (although the power shape and degree of irradiation are typical of

beginning of life). The nominal full power of the LOFT core is 50 MW.

Heat losses to the environment are modelled by means of a constant ambient temperature and a set of

fixed heat transfer coefficients from the outside walls of the primary system pipework, vessel, and

pressuriser, and the steam generator. The htc's and the losses at normal operating temperature are as

follows:

Ambient temperature = 311 K

Vessel and pipework htc = 10.74 W/n**2K loss = 174 kW

Pressuriser wall htc = 3.019 W/m**2K loss = 6 kW

Steam generator wall htc = 3.385 W/m**2K loss = 20 kW

The total heat loss of 200 kW is significant compared with decay heat levels for long transients.

323. Mass sources and sinks

Mass sources modelled in the input deck include the pumped ECC injection, the primary coolant pump

injection, the feedwater and auxiliary feedwater systems. Each of these sources are modelled by time

dependent volumes and junctions in conjunction with the trip and control systems, as described elsewhere in the present document. The charging system, although used prior to the start of each transient,

is disabled during transients and is not modelled in the deck. There is no control, therefore, of the primary coolant mass inventory during steady state operation, and so the initial inventory has to be

specified separately at the start of a steady state run.

Mass sinks are identified with the modelled break(s) during LOCA transients, with relief valve flows,

and with the main steam and main steam bypass flow. The flow rate is determined from the upstream

conditions, the valve or break area, the multiplier, using the RELAP5/MOD2 break flow model, (the

AEEW-R 2454 -14-
downstream conditions being such that the flows are choked).

4. Conclusions

The LOFT input dataset described in this document for RELAP5/MOD2 represents the latest information available for the LOFT system, taking into account also results from analyses performed in the

U.K. Modifications have been made, therefore, in accordance with analysis results.

The dataset includes representation of hardware and trip systems for loss-of-coolant experiments and

intact primary circuit transients, thereby keeping all the data in a single dataset.

5. References

1. "RELAP5/MOD2 Code Manual" NUREG/CR-4312, EGG-2396

(December 1985) EG&G (Idaho), Inc.

2. "RELAP5/MOD2 Validation for Sizewell 'B' Application" PWR/THSG/P28 issue 2,

(October 1988) I.L. Hirst

3. "LOFT System and Test Description (5.5-ft Nuclear Core LOCEs)" NUREG/CR-0247, TREE1208

(July 1978) D.L. Reeder

4. "LOFT Input Data Deck for RELAP5" EGG-LOFT-5199

(July 1980) E.J. Kee, P.J. Schally, and L. Winters,

5. "Post test analysis of OECD LOFT experiment LP-SB-3 using RELAP5/MODI" GD/PE-N/482,

(February 1985) C. Harwood.

6. "RELAP5/MOD2 Calculation of OECD LOFT test LP-SB-3" GD/PE-N/535(Rev)

(April 1986) G. Brown, and C. Harwood.

7. "RELAP5/MOD2 Calculations of OECD LOFT test LP-SB-1" GD/PE-N/544(Rev)

(November 1986) P.C. Hall, and G. Brown.

8. "RELAP5/MOD2 Calculations of OECD LOFT test LP-SB-2" GD/PE-N/606(Rev)

(December 1987) P.C. Hall.

9. "RELAP5/MOD2 Calculations of OECD LOFT test LP-FW-1" GD/PE-N/597

(June 1988) M.G. Croxford, C. Harwood, and P.C. Hall.

10. "RELAP5/MOD2 Analysis of LOFT Experiment L9-4" GD/PE-Nf721

(December 1988) M.B. Keevill.

11. "Internal LOFT Reactor Vessel Core Bypass Rows" RE-A-81-011, USNRC-P394

(November 1981) W.C. Jouse

12. "Dimensional Data - Steam Generator" Private Communication from INEL

13. "RELAP5/MOD2 analysis of LOFT Experiment L9-3" AEEW-R 2435

(December 1988) J C Birchley

AEEW-R 2454 -15-
tU

01

Ln

Table la Intact loop volume data

comp Vol Lan Area Volume Hyd Elev E9ev Comp Description

Num Num Diam Change Outlet Type

(m) (m2) (m3) (M) (m) (M)

100 01 1.4458 0.064140 0.09274 02858* 0.0 0.0 BRANCH Core banel., vessel nozzle

102 01 4.1275 0.000682 0.002815* 0.0295* 0.0 0.0 SNGLVOL Break line, ID = 1.16 inch

104 01 0.286 0.064160 0.01835 0.2858* 0.0 0.0 SNOLVOL Break connection

105 01 1.0506 0.064140 0.06739 0.2858* 0.0 0.0 BRANCH Pipe to surge line, elbow

110 01 1.1061 0.05815* 0.064318 0.2721* 0.0 0.0 BRANCH Pipe from surge line, venturi

112 01 1.3889 0.05378* 0.079697 0.2703* 0.0 0.0 PIPE elbow, half of reducer

02 0.70769 0.08190* 0.057961 0.3229* 0.246 0.246 Half of reducer

114 01 0.63 0.5122* 03227 0.0102 0.513 0.759 BRANCH SG inlet plenum

115 01 0.5972 0.1513 0.090360 0.01022 0.5972 1.3562 PIPE SO tubes upside

02 0.3048 0.1513 0.04611* 0.01022 0.3048 1.6610 SG tubes upside

03 0.6096 0.1513 0.09223* 0.01022 0.6096 2.2706 SG tubes upside

04 0.6096 0.1513 0.09223* 0.01022 0.6096 2.8802 SO tubes upside

05 0.4612 0.1513 0.06978* 0.01022 0.4612 3.3414 SO tubes U-bend

06 0.4612 0.1513 0.06978* 0.01022 -0.4612 2.8802 SO tubes U-bend

07 0.6096 0.1513 0.09223* 0.01022 -0.6096 2.2706 SG tubes downside

08 0.6096 0.1513 0.09223* 0.01022 -0.6096 1.6610 SO tubes downside

09 0.3048 0.1513 0.04611* 0.01022 -0.3048 1.3562 SO tubes downside

10 0.5972 0.1513 0.09036* 0.01022 -0.5972 0.759 SG tubes downside

116 01 0.63 0.5318* 0.335 0.0102 -0.513 0.246 BRANCH SG outlet plenum

118 01 0.547 0.07989* 0.0437 0.3189* -0.498 -0.252 PIPE 52 degree elbow

02 0.689 0.06705* 0.0462 0.2922* -0.689 -0.941 Half of seducer

03 0.550 0.0634 0.03544* 02841* -0.356 -1.297 90 degree elbow

120 01 0.76 0.0634 0.04818* 0.2841* 0.0 -1.297 BRANCH Pipe, inlet to pnmp suction
Table Ia Intact loop volume data (continued) I

bJ

IN

L.-

Comp Vol Length Area Volume Hyd Elev Elev Comp Descpon

Num lur Diam Change Outlet Type ...... (M) (2n2) (m3) (M) (M) (m)

125 01 1.003 0.06112" 0.0613 0.2790' 0.521 -0.776 BRANCH Half of pump suction, elbow

130 01 0.457 0.041360 0.0189 0.2295" 0.457 -0.319 SNGLVOL Half of reducer, PCP 1 inlet

135 01 2.7049* 0.0366 0.099 - 0.319 0.0 PUMP PCP 1

140 01 0.502 0.0366 0.01837" 0.21590 0.0 0.0 SNGLVOL PCP 1 outlet pipe, elbow

145 01 1.4084 0.04494* 0.0633 0.2392' 0.0 0.0 BRANCH Pipe, reducer, PCI'P outlet

150 01 0.4966 0.0634 0.03148' 0.2841' 0.0 0.0 BRANCH Half of pump outlet

155 01 1.003 0.061110 0.0613 0.2790" 0.521 -0.776 BRANCH Half of pump suction, elbow

160 01 0.457 0.04136' 0.0189 0.2295" 0.457 -0.319 SNGLVOL Half of reducer, PCP 2 inlet

165 01 2.7949* 0.0366 0.099 - 0.319 0.0 PUMP PCP 2

170 01 0.514 0.0366 0.01881' 0.2159* 0.0 0.0 BRANCH elbow, inlet of PCI outlet

175 01 0.559 0.0634 0.03544* 0.28410 0.0 0.0 PIPE 90 degree elbow

02 0.613 0.0634 0.03886' 0.28410 0.0 0.0 Pipe section, elbow

180 01 1.01 0.06343' 0.06406 0.2842* 0.0 0.0 BRANCH Pipe to ECC line
tIj

bj

4

Ln

OD

I

Table Ia Intact loop volume data (continued)

Comp Vol l.ngth Area Volume Hyd Elev Elev Comp Descriptio

Num Nun Diam Change Outlet Type

(in) (m2) (m3) (in) (m) (m)

181 01 2.997 0.0006818 0.0020430 0.000549" 0.0 0.0 BRANCH Break line ID-1.16 in boriz

182 01 0.806 0.0006818 0.000549* 0.000549* -0.806 -0.806 BRANCH Bre4k line IDM1.16 in vedical

184 01 0.284 0.06356" 0.01805 0.2845* 0.0 0.0 SNGLVOL Cold leg break connecting pipe

185 01 1.152 0.06379" 0.07349 0.2850* 0.0 0.0 BRANCH Pipe from ECC line, nozzle

910 01 1.0 0.0035 0.00350 0.00669* 0.0 0.0 TMDPVOL PCP I injection volume

911 01 1.0 0.0035 0.0035" 0.00669" 0.0 0.0 TMDPVOL PCP 2 injection volume
9

til

Ln

I

Table lb Intact loop junction data

Comp Jun Volume number Area Junction Loss coefficient Description

Num N um Prom To [Rag Forward Reverse (m2) evcahs

100 01 2520000 1000000 0.0634 000002 0.1 0.1 RPV nozzle intact loop hot leg

02 1000100 1050000 0.06344" 000000 0.1 0.1 RPV nozzle to pr ser tee

03 1000000 1850100 0.06344* 000000 7200.0 7200.0 Bypass flow across nozzles

101 01 1040100 1020000 0.000682 100102 1.26 1.26 Break - junction with hot leg

103 01 1020100 8050000 0.0001266 000120 -0.93 -0.81 Break - valve ID = 0.5 inch

105 01 1050100 1100000 0.05815* 000000 0.12 0.12 Pressurier tee hot leg side

02 1040100 1050000 0.05815* 000000 0.0 0.0 Pressuriser tee RPV side

110 01 1100100 1120000 0.05738* 000000 0.15 0.15 Pressutiser tee SO side

112 01 1120100 1120200 0.05738* 010000 0.2 0.2 Hot leg pipe

114 01 1120100 1140000 0.0512 000100 0.0 0.0 Hot leg pipe to SG inlet plenum

02 1140100 1150000 0.1513' 000100 0.0 0.0 SG inlet plenum to SG tubes

115 01 1150100 1150200 0.1513* 000000 0.0 0.0

02 1150200 1150300 0.15130 000000 0.0 0.0

03 1150300 1150400 0.1513' 000000 0.0 0.0

04 1150400 1150500 0.1513* 000000 0.0 0.0 SO tubes

05 1150500 1150600 0.15130 000000 0.0 0.0

06 1150600 1150700 0.1513" 000000 0.0 0.0

07 1150700 1150800 0.1513" 000000 0.0 0.0

08 1150800 1150900 0.15130 000000 0.0 0.0

09 1150900 1151000 0.1513" 000000 0.0 0.0

116 01 1150100 1160000 0.1513" 000100 0.0 0.0 SG tubes to SO outlet plenm

02 1160100 1180000 0.07989' 000100 0.0 0.0 SG outlet plenum outlet

0.0" Indicates input as 0.0 and value calculated by code.

Negative loss coefficients imply multipliers for single- and two-phase flow
gI~

U'

to

01

Table lb Intact loop junction data (continued)

Comp Jun Volume namber Area Junction "os coefficient JDes=ipton Num Nun i Prom To nag Forward Reverse

. I _ (m2) evcahs

118 01

02

120 01

02

03

125 01

135 01

02

145 01

02

150 01

02

155 01

165 01

02

175 01

180 01

02

1180100 1180200

1180200 1180300

1180100 1200000

1200100 1250000

1200100 1550000

1250100 1300000

1300100 1350000

1350100 1400000

1400100 1450000

1450100 1500000

1700100 1500000

1500100 1750000

1550100 1600000

1600100 1650000

1650100 1700000

1750100 1750200

1750100 1800000

1800100 1850000

0.06705*

0.0634*

0.0634*

0.0317

0.0317

0.04136*

0.0366*

0.0366*

0.0366*

0.04494*

0.0183

0.0634*

0.04136*

0.0366*

0.0366*

0.0634*

0.0634*

0.0634*

000000

000000

000000

000000

000000

000000

000000

000000

000000

000000

000000

000000

000000

000000

0o0000

0.083

0.104

0.1

0.4

0.4

0.13

0.017

0.05

0.0

0.1

0.1

0.0

0.13

0.017

0.05

0.0

0.0

0.083

0.104

0.1

OA

0.4

0.13

0.017

0.05

0.0

0.1

0.1

0.0

0.13

0.017

0.05

0.0

0.0

0.0

Crissover leg pipe

Puinp suction tee inlet

Pump muio outlet PCP' I side

Pump suction outlet PCP 2 side

PCP I inlet pipe

PCP I entry

PCIPI exit

PCP I dischage to discharge tee

PCP discharge tee PCP I side

PCP discharge tee PCI 2 side

P discharge tee outlet to ILCL

PCP 2 inlet pipe

PCI 2 entry

PCP 2 exit

ULCL leg 45 degree bead

Inlet to pumrp side of ECC tee

000000 0.0 PCI side of ECC tee I 4 1

0.0* Indicates input as 0.0 and value calculated by code.
U'

Table lb Intact loop junction data (continued)

Comp Jun Volume number Area Junction Loss coefficient Description

Num Num From To Flag Frward Reverse

_ (m2) evcahs

181 01 1840100 1810000 0.0006818 001001 1.26 1.26 Break line connection tee

182 01 1810100 1820000 0.0006818 001000 1.26 1.26 Break line elbow connection

183 01 1820100 8050000 0.0000608 001200 -0.93 -0.81 Orifice - simulated 1.84in break

185 01 1850100 2020000 0.0634 000001 2.8 2.8 ECC tee connection to vessel

901 00 9100000 1400000 0.0035* - 0.0 0.0 PC 1 injection

902 00 9110000 1700000 0.0035 - 0.0 0.0 PCP 2 injection

I

o- 0.0" Indicates input as 0.0 and value calculated by code. I
sIb

U'

1%)

1%)

Table Ic Intact loop beat slab data

ieat *i Gemety Left Right Area/Length Interval Material Left Right

Structure Type Boundary Boundary /Factor Number Boundary Boundary

Number Volume Volume (m2Im/mO) (m) (m)

60-001

-003

-004 4)05

-007

-008

-009

-010

1001-01

-003

4)05

-006

-007

-008

-009

-010

-012

-012

-013

-014

CYL

CYL

LP-SB-3

11501

11502

11503

11504

11505

11506

11507

11508

11509

11510

10001

10401

10501

11001

11201

11802

11803

12001

15001

17501

17502

18001

18501

18401

51501

51502

51503

51504

51505

51505

51504

51503

51502

5150100000000000000

562.36

562.36

1124.71

1124.71

849.063

849.063

1124.71

1124.71

562.36

562.36

1.4458

0.2866

1.0506

1.06124

1.38893

0.68900

0.55900

0.76000

0.49660

0.55900

0.61300

1.01000

1.15200

0.284

1-8

1-5

Inconei 0.0051054 0.00634898

S-Steel 0.142 0.178
U1

Table Ic Intact loop heat slab dafta (continued)

Heat Geomeny Left Right Area/Length Interval Material Left Right

Strcture Type Boundary Boundmry /Factor Number Bounday Boundat•y

Number Volume Volume (m2/mbfn) (m) (m)

1002-001 CYI 11202 0 0.70800 1 - 5 S-Steel 0.16250 0.20300

-002 11801 0 0.54700

1003-001 CYL 12501 0 1.00000 1 - 5 C-Steel 0.10800 0.13650

-002 13001 0 0.45700

-003 14001 0 0.50200

14501 0 1.40840

-005 15001 0 1.00300

-006 16001 0 0.45700

-007 17001 0 0.51400

1004-001 CYL 11401 0 0.25000 1 - 5 C-Steel 0.68580 0.77470

-002 11601 0 0.25000 thi
t•3

IU

t•

I4

Table 2a Reactor vessel volume data

Comp Vol Length Area Volume Hyd Elev Elev Comp Descripuion

Num Num Diam Change Outlet Type

(m) (m2) (W3) (M) (M) (M)

200

202

205

210

215

220

223

225

01

01

01

01

02

03

04

05

06

01

01

01

02

03

04

01

0.1874

0.2852

0.2814

0.958

0.579

0.657

0.559

0.559

0.520

0.360

0.370

1.382

1.236

1.118

1.250

0.520

0.268

0.268

0.268

0.142

0.142

0.142

0.142

0.142

0.142

0.740

0.790

0.02911

0.02911

0.02911

0.02911

0.250

0.05022*

0.07643*

0.07542*

0.13604*

0.08221*

0.09329"

0.07938*

0.07938*

0.07384*

0.2664*

0.2923*

0.04023*

0.03598*

0.03254*

0.03639*

0.13*

0.172

0.178

0.172

0.102

0.102

0.102

0.102

0.102

0.102

0.97067*

1.00293*

0.19252*

0.19252*

0.19252*

0.19252*

0.095

0.1874

-0.2852

-0.2814

-0.958

-0.579

-0.657

.0.559

-0.559

-0.520

-0.360

-0.370

-1.382

-1.236

-1.118

-1.250

0.520

0.330

.0.1426

-0.1426

-1.392

-1.961

-2.618

-3.177

-3.736

-. 256

-4.616

-4.986

-1.382

-2.618

-3.736

-4.986

-3.736

ANNULUS

BRANCH

ANNULUS

ANNULUS

BRANCH

SNGLVOL

ANNULUS

BRANCH

Inlet anmulus upper

Inlet annulus middle

Inlet annulus lower

Downcomer

Lower plenum upper

Lower plenum lower

Vessel filler gap

Lower core suppoat
9

I3

U'

Lq

Table 2a Reactor vessel volume data (continued)

Comp Vol Length Area Volume Hyd Elev Elev Comp Description

Nuim Num Diam Change Outlet Type

(M) (m2) (m3) (M) (m) (M)

230 01 0.2795 0.1705 0.047650 0.012 0.2795 -3.4565 PIPE Active core

02 0.2795 0.1705 0.04765" 0.012 0.2795 -3.177

03 0.2795 0.1705 0.047650 0.012 0.2795 -2.8975

04 0.2795 0.1705 0.04765" 0.012 0.2795 -2.618

05 0.2795 0.1705 0.047650 0.012 0.2795 -2.3385

06 0.3775 0.1705 0.06437" 0.012 0.3775 -1.961

235 01 0.559 0.015 0.00939" 0.003 0.559 -3.177 PIPE Corn bypass

02 0.559 0.015 0.00839' 0.003 0.559 -2.618

03 0.657 0.015 0.009890 0.003 0.657 -1.961

240 01 0.559 0.297 0.16602" 0.145 0.559 -1.402 BRANCH Upper end box centefupo

245 01 0.559 0.297 0.16602" 0.145 0.559 -0.843 BRANCH Upper support X-flow

250 01 0.7004 0.114 0.07985* 0.131 0.7004 -0.1426 BRANCH Upper flow skirt vol

251 01 0.700 0.183 0.1281* 0.214 0.700 -0.1426 SNGLVOL Dead end fuel modules

252 01 0.2852 0.201 0.05732' 0.5059* 0.2852 1426 BRANCH Upper plenum lower

255 01 0.7114 0.288 0.20488* 0.6055* 0.7114 0.854 BRANCH Upper plenum bottom

260 01 0.712 0.244 0.1737' 0.55740 0.712 1.566 SNGLVOL Upper plenum top

U'

* Indicates input as 0.0 - value calculated by code
U1

Table 2b Reactor vessel junction data

CDMp Jun Volume umber Area Junction Loss coefficient Descriptio

Num Num I HPom To Flag FoIward Reverse

(m2) evcahs

202

1206

I

I

210

215

222

223

224

01

02

00

01

02

03

04

05

01

02

03

00

01

02

03

00

2050100 2100000 1 0.142*

2020000 2000000 0.268*

2020100 2050000 0.268*

2100100 2100200

2100200 2100300

2100300 2100400

2100400 2100500

2100500 2100600

2100100 2150000

2150100 2200000

2150000 2250000

0.142*

0.142*

0.142"

0.142*

0.142*

0.142*

0.74*

0.15

0.02911*

0.02911*

0.02911*

0.02911*

0.02911 *

000000

000000

000000

000000

000000

000000

000000

000000

0.0

0.0

0.0

0.0

0.0

2.0

0.005

1.5

000000 0.0

000000 0.0

000000 0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

2.0

0.005

1.5

52.0

0.0

0.0

0.0

45.0

Inlet annulus upper to middle

Inlet annulus middle to lower

Inlet annulus to downcomer

Vessel downcomer

Downcomer to lower plenum

Lower plenum to lower head

Lower plenum to lower support

Cold leg to vessel filler gap

vessel filler gap

Filler gap to lower head

1850100 2230000 000000 52.0

2230100 2230200

2230200 2230300

2230300 2230400

2230100 2200100

000000

000000

000000

0.0

0.0

0.0

000000 45.0

I 1 .1.

* dicates input as 0.0 and value calculated by code.
U'q

tLn

Table 2b Reactor vessel junction data (continued)

Comp Yon Volume number Area Junction Loss coefficient Descipton Num lqum Prom To Flag Forward Reverse

(m2) evcahs

225 01 2250100 2300000 0.0975 000000 1.5 1.5 Core entry

02 2250100 2350000 0.015* 000000 21.0 21.0 Core bypass entry

230 01 2300100 2300200 0.1705* 000000 0.0 0.0

02 2300200 2300300 0.1440" 000000 0.66 0.66

03 2300300 2300400 0.1705* 000000 0.0 0.0 Core

04 2300400 2300500 0.1440" 000000 0.66 0.66

05 2300500 2300600 0.1705* 00000 0.0 0.0

235 01 2350100 2350200 0.0150 000000 0.0 0.0

02 2350200 2350300 0.015 000000 0.0 0.0 Core bypass

240 01 2300100 2400000 0.120 000000 1.5 1.5 Core exit

02 2350100 2400000 0.015" 000000 21.0 21.0 Core bypass exit

245 01 2400100 2450000 0.297* 000000 0.0 0.0 Upper msupoe structure

02 2450100 2510000 0.183* 000000 0.0 0.0

250 01 2450100 2500000 0.1140 000000 0.0 0.0 Upper support structure

252 01 2520100 2550000 0.201* 000000 0.006 0.006 Upper plenum lower to bottom

01 2520000 2500100 0.114* 000000 0.003 0.003 Upper structure to upper plenm

255 01 2550100 2600000 0.244" 000000 0.03 0.03 Upper plenum bottom to top

toJ

I4

0 Indicates input as 0.0 and value calculated by code.
ul

I

Table 2c Reactor vessel beat slab data

Heat Geomety Left Right Area/lwugtb Interval Material Left Right

Structure Type Boundary Boundary /Factor Number Boundary Boundary

Number Volume Volume (m2/m/mO) (m) (m)

2000-001

-002

2001-001

-002

-003

-O09

-004

-006 -007

-OM8

-003

-004

2050-001

2100-001

-002

-003

-004

-001

-008

2200-001

2231-001

2232-001

-002

-003

CmL

CmL

CmL

CmL

20001

20201

0

0

0

0

0

0

0

0

0

20501

21001

21002

21003

21004

21005

21006

21501

22001

0

0

20001

20201

20501

21001

21002

21003

21004

21005

21006

22301

22301

22302

22302

22303

22303

22304

22304

22304

0.1874

0.2852

0.187

0.285

0.281

0.958

0.579

0.657

0.559

0.559

0.520

0.2814

0.958

0.579

0.657

0.559

0.559

0.520

0.360

0.370

1.680

1.382

0.802

0.434

1.118

1.250

1-5

1-5

1-5

1-5

1-5

1-5

1-5

S-Steel 0.5080

S-Steel 0.381

S-Steel 0.5010

S-Steel 0.4700

0.7264

0.419

0.7264

0.7264

0.092

0.8725

0.8247

Recr

CmL

CmL

22301

22302

22302

22303

22304

0

0

0

0

0

0

C-Steel 0.0

C-Steel 0.7328

C-Steel 0.7328
sr~

'0

Table 2c Reactor vessel heat slab data (continued)

Heat Geometry Left Right Area/Length Interval Material Left Right

Stractuiu Type Boundary Boundary /Factor Number Boundary Boundary

Number Volume Volume (m2/m/fm0) (m) (M)

2250-001

M02

-003

-0M4

-005

-06

-007

-O8

-09

-010

2251-001

2300-001

-002

-03

-005

-O6

CmL

CmL

CmL

22501

23001

23002

23003

23004

23005

23006

24001

24501

25001

22501

00000000000

0 23001

0 23002

0 23003

0 23004

0 23005

0 23006

0.5200

0.2795

0.2795

0.2795

0.2795

0.2795

0.3775

0.5590

0.5590

0.8430

0.520

363.35

363.35

363.35

36335

363.35

363.35

1-5

1-5

1-67

8-10

1-67

8- 10

1-67

8- 10

1-67

8- 10

1-67

8- 10

1-67

8- 10

S-Steel

S-Steel 0.282

U02

Gap

Zircaloy

U02

Gap

TCWaloy

U02

Zircaloy

U02

2Thcaloy U02

Gap

Zircaloy

U02

Gap

zihcaloy

0.0

0.004647

0.004742

0.0

0.004647

0.004742

0.0

0.004647

0.004742

0.0

0.004647

0.004742

0.0

0.004647

0.004742

0.0

0.004647

0.004742

0.300 0.380

0.300

0.004647

0.004742

0.005359

0.004647

0.004742

0.005359

0.004647

0.004742

0.005359

0.004647

0.004742

0.005359

0.004647

0.004742

0.005359

0.004647

0.004742

0.005359

o 4 -
6Pb

Table 2c Reactor vessel beat slab data (contiued)

Heat Geomewr Left Right Ar/eaAngth Interval Material Left Right

Stfacture Type Bounary Boundary /Factor Number Bounday Bounary

Number Volume Volume (m2/nm/m0) (M) (m)

2400-001 CYL 24001 0 0.559 1 - 5 S-Stel 0.282 0.310

-002 24501 0 0.559

2510-001 RECl 25001 25101 1.800 1 -5 S-Steel 0.0 0.010

2551-001 RECr 25201 0 0.300 1 -5 S-Steel 0.0 0.005

-002 25501 0 0.700

-003 26001 0 1.000

2552-001 CYL 25501 0 0.854 1 - 5 C-Steel 0.381 0.474

2601-001 CYL 26001 0 0.712 1 - 5 C-Steel 0.381 0.728

2602-001 RECi" 26001 0 0.712 1-5 C-Steel 0.0 0.474

Ia

0•
Table 3a Broken loop volume data

U'

w

qNJ

Comp Vol Length Area Volume Hyd Elev Elev Comp Description

Num Nm Diam Change Outlet Type ________ (in) (m2) (m3) (in) (mn) (in) _________

300

305

310

315

335

340

345

350

370

380

01

01

01

01

02

01

01

01

01

02

01

02

03

01

02

03

0.876

0.698

1.5001

0.488

1.6085

0.7495

0.698

0.974

0.0488

1.6085

0.7190*

1.80410

1.50130

1.1791*

1.2371"

1.2603*

0.0634

0.0634

0.04520

0.01109"

0.04830

0.0634

0.0634

0.0634

0.01109*

0.0483*

0.0388

0.0388

0.0776

0.0776

0.0388

0.0388

0.05554"

0.04425"

0.06785

0.00541

0.0777

0.04752*

0.04425*

0.06175*

0.00541

0.0777

0.0279

0.0700

0.1165

0.0915

0.0480

0.0489

0.2841" 0.0

0.28410 0.0

0.240* 0.0

0.1188* 0.0

0.248* 0.0

0.2841* 0.0

0.2841* 0.0

0.2841* 0.0

0.3758* 0.0

0.2480* 0.0

0.2223* 0.64

0.2223* 0.0

0.3143" 0.0

0.3143" 0.0

0.2223* -0.64

0.2223* 0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.64

0.64

0.64

0.64

0.0

0.0

BRANCH

BRANCH

BRANCH

PIPE

BRANCH

BRANCH

BRANCH

PIPE

PIPE

PIPE

Vessel nozzle BLHL

BLHL to RADS tee

BLHL contraction

Pipe to isolation valve

Vessel nozzle BLCL

BLCL to RADS tee

BLCL contraction

Pipe to isolation valve

I RABS - BLCL side

RABS - BLHL side

* Indicates input as 0.0 - value calculated by code
f- Table 3b Broken loop junction data

UI

I

Comp Jun Volume number Area Junction Lous coefficient Description

Num Num From To Flag Forward Reverse

S.___ (m2) evcaIs

300 01 2520100 3000000 0.0634 000002 0.0 0.0 Broken loop hot leg nozzle

02 3000100 3050000 0.0634* 000000 0.1 0.1 BLHL nozzle connection to pipe

305 01 3050100 3100000 0.04523* 000000 0.1 0.1 BLHL connection to RABS tee

310 01 3800100 3100000 0.0388 000001 0.84 0.84 RADL tee to RABL pipe - HL side

02 3100100 3150000 0.008365 000100 0.0 0.0 RABL tWe to BLHL contraction

315 01 3150100 3150200 0.01109 000100 0.0 0.0 BLHL contraction junction- -lL

335 01 2020100 3350000 0.0634 000002 1.0 1.0 Broken loop cold leg nozzle

02 3350100 3400000 0.06340 000000 0.1 0.1 BLCL nozzle connection to pipe

340 01 3400100 3450000 0.0634" 000000 0.1 0.1 BLCL connection to RABL tee

345 01 3450000 3700000 0.0388 010000 0.84 0.84 RADL tee to RADL pipe - CL side

350 01 3500100 3500200 0.01109 000100 0.0 0.0 BLCL contraction junction - CL

370 01 3700100 3700200 0.0388 000000 0.28 02.8 RABL pipe junction - CL side

02 3700200 3700300 0.0388 000000 0.84 0.84

375 01 3700100 3800000 0.07760 000000 14000.0 14000.0 RABL valve

380 01 3800100 3800200 0.0388 000000 0.84 0.84 RABS pipe junction - CL side

02 3800200 3800300 0.0388 000000 0.28 0.28

* Indicates input as 0.0 and value calculated by code.
gob

El'

wI

Table 3c Broken loop beat slab data

Heat jGeoff,"y Left Right AresaLength lImerval material ILeft Right

Structure Type Boundary Bomuda /Fator Number Boundary Bourdary

Number Volume Volume (m2/m/m0) (m) _ (M)

3000-.01

-003

3151-001

3152-001

3350-001

4)02

3501-001

3502-001

3700-001

-O2

-003

-004

-405

-0O6

CmL

CYL

CYL

CmL

CmL

CmL

CmL

30001

30501

31001

31501

31502

33501

33502

33503

35001

35002

37001

37002

37003

38001

38002

38003

0.876

0.698

1.424

0.488

1.6085

0.7495

0.6980

0.9740

0.488

1.6085

0.7251

1.8200

2.9055

2.2898

1.2331

1.1065

1-5

1-5

1-5

1-5

1-5

1-5

1-5

1-5

1-5

S-Steel 0.142

S-Steel

S-Steel

S-Steel

S-Steel

S-Steel

S-Steel

S-Steel

S-Stool

0.055

0.0865

0.142

0.055

0.0865

0.111

0.178

0.178

0.1095

0.178

0.178

0.1095

0.1365
tij

f Table 3d Broken loop volume data (for tests using SO and pump simulators)

Camp Vol LAngth Area Volume Hyd Elev Elev Conp Description

Num Num Diam Change Outlet Type

(M) (m2) (m3) (M) (M) (M)

315 01 0.367768 0.00836* 0.0030767 0.1032* 0.127 0.127 PIPE Line to SO simulator

02 0.552201 0.00847* 0.0046762 0.1038* 0.552201 0.679201 Line to SO simulator

03 0.993378 0.08663* 0.0860554 0.3321* 0.993978 1.673179 SG simulator upside

04 0.993378 0.08663* 0.0860554 0.124 0.993978 2.667157 SO simulator upside 05 0.849744 0.10563* 0.0897552 0.3667* 0.457202 3.124359 SO simulator top

06 0.849744 0.10563* 0.0897552 0.3667* -0.457202 2.667157 SO simulator top 07 0.993378 0.08663* 0.0860554 0.124 -0.993978 1.673179 SO simulator downside

08 0.993378 0.08663* 0.0860554 0.3321 -0.993978 0.679201 SO simulator downside

09 1.37135 0.01329* 0.0182303 0.1301* -1.37135 -0.692149 Pump suction downside

10 1.365029 0.04005* 0.0546687 0.2258* -0.520701 -1.21285 Pump suction bottom

11 1.674812 0.01090* 0.018249 0.1178* 1.212851 0.0 Pump suction upside 12 0.545209 0.05195* 0.0283241 0.2572* 0.0 0.0 Pump simulator ¢oI

d•

!

* Indicates input as 0.0 - value calculated by code
9~

L2'

Table 3e Broken loop junction data (for est using SG and pumnp simulators)

Comp Jun Volume number Aea Junction coefficient Description

Num Num lrom To Flag Forward Reverse

(m2) evcahs315 01 3150100 3150200 0.008365 000000 0.2 0.2

02 3150200 3150300 0.008365 000100 0.0 0.0

03 3150300 3150400 0.032603 000000 93.9 93.9

04 3150400 3150500 0.032603 000000 93.9 93.9

05 3150500 3150600 0.105626 000000 0.4 0.4

06 3150600 3150700 0.032603 000000 93.9 93.9

07 3150700 3150800 0.032603 000000 93.9 93.9

08 3150800 3150900 0.008365 000100 0.0 0.0

09 3150900 3151000 0.008365 000000 0.2 0.2

10 3151000 3151100 0.008365 000000 4.1 4.1

11 3151100 3151200 0.004640 000100 0.4 0.4 m

' indicates ft as 0.0 amd value calculated by code.
N

U'

m~.

Table 3f Broken loop beat slab data (for tes unug SG and pump simultors)

Heat Geometry LeAf Right Arc4egth Interval Material Lea Right

Structure Type Bouadary Bounday /pacto Number Boutdary Boundary

Number Volume Volume (2/UImO) (m) (in)

3151-001 CYL 31501 0 0.3678 1 - 5 S-Steel 0.055 0.178

-0M2 31502 0 0.5522

-003 31503 0 0.9940

-004 31504 0 0.9940

-005 31505 0 0.8497

-006 31506 0 0.8497

-047 31507 0 0.9940

-008 31508 0 0.9940

-009 31509 0 1.3714

-010 31510 0 1.3650

-011 31511 0 1.6748

-012 31512 0 0.5452 w
9

tIZn

I3

Table 4a Pisswiser volume data

Comp Vol Length Area Volume Hyd Elev Elev CoMp Descipon

um Numn Diam Change Outlet Type

(M) (m2) (m3) (M) (m) (M)

400 01 2.300 0.00145 0.00334* 0.04297* 0.540 0.540 SNGLVOL Pzr surge line - PCS side

405 01 2.300 0.0145 0.00334* 0.04297* 0.300 0.840 PIPE Prenvdser surge line

02 2.300 0.0145 0.00334* 0.042970 0.300 1.140

415 01 0.1815 0.3769* 0.0684 0.6927* 0.1815 1.3215 PIPE Pressuriser vessel

02 0.1524 0.5499* 0.0838 0.83670 0.1524 1.4739

03 0.3967 0.5653 0.2243* 0.8484* 0.3967 1.8706

04 0.5299 0.5653 0.2990* 0.8484* 0.5289 2.3995

05 0.3967 0.5653 0.2243* 0.8484* 0.3967 2.7962

06 0.1943 0.3767* 0.0732 0.6926* 0.1943 2.9905

07 0.1029 0.1380* 0.0142 0.4192* 0.1029 3.0934

420 01 0.1029 0.1380* 0.0142 0.4192* 0.1029 3.1963 BRANCH Pressuriser top

430 01 1.0 1.0 1.0* 1.1284* 0.0 3.0934 TMDPVOL Dummy volume

440 01 6.322 0.000336 0.00213* 0.0207* 3.0934 3.0934 BRANCH Pressuiser spray

805 01 1.0 0.1* 0.1 0.3568* 0.0 3.1963 TMDPVOL Containment from SRV

810 01 1.0 0.10 0.1 0.3568* 0.0 3.1963 TMDPVOL Containment from PORV

* Indicates inpu as 0.0 - value calculated by code
ul

I

(OD

I

Table 4b Pressuriser junction data

Comp Jun Volume nuimber Area Junction Loss coefficien Don

Num Num From To Flag Forward Reverse

(m2) evcahs

401 00 1100000 4000000 0.001450 110002 0.93 0.93 MU.L to surge line connection

402 00 4000100 4050000 0.00145" 000000 0.93 0.93 Surge line pipe junction

405 01 4050100 4050200 0.00145 000000 0.0 0.0 Surge line pipe junction

410 00 4050100 4150000 0.00145* 000000 0.93 0.93 Surge line connection to pzr

415 01 4150100 4150200 0.3769* 000000 0.0 0.0 Pressuriser vessel junction

02 4150200 4150300 0.5499* 000000 0.0 0.0 Pessriser vessel junction

03 4150300 4150400 0.56530 000000 0.0 0.0 Pressuriser vessel junction

04 4150400 4150500 0.5653* 000000 0.0 0.0 Pressuriser vessel junction

05 4150500 4150600 0.3767* 000000 0.0 0.0 Pressuriser vessel junction

06 4150700 4150700 0.1380* 000000 0.0 0.0 Pressuriser vessel junction

420 01 4150100 4200000 0.1380* 000000 0.0 0.0 Pza vessel to top connection

431 00 4300000 4200000 0.1380" 000000 0.0 0.0 Dummy volune to pressuriser

440 01 1500000 44,000 0.0003363 000000 0.0 0.0 ILCL connection to spray line

445 00 4400100 4150100 0.0003345 000000 0.0 0.0 Pressuiser spray valve

450 00 4200100 8050000 0.0000156 000100 0.0 0.0 Safety relief valve

455 00 4200100 810W000 0.0000134 000100 0.0 0.0 Pilot operated relief valve

* Indicates input as 0.0 and value calculated by code.
U'j

Zr

Table 4c Pressuaiser heat slab data

Heat OeoGnety Left Right Are/Length Interval Material Left Right

Structu" Type Boundary Boundary /Factor Number Boundary Boundary

Number Volume Volume (m2/mfmO) (m) (M)

4152-001 CYL 41501 0 0.1815 1-5 C-Steel 0.42291 0.49911

-002 41502 0 0.1524

-003 41503 0 03967

-004 41504 0 0.5289

-005 41505 0 03967

-006 41506 0 0.1943

4153-001 CYL 41507 0 0.1029 1 

- 5 C-Steel 0.2032 0.3683

-002 42001 0 0.1029

4201-001 RECT 42001 0 0.130 1 

- 5 C-Steel 0.0 0.18415

I
gt•

u1:, 0l

0

1

Table 5a Stewam generator sccaWay volume data

CoMP Vol L An& Velume Hyd m-v Elev Cump 1 Duipdon

Nam Nan Dian Oae Outlet Type

(m__ _ (,n) (,n) (ma) _W_ ___)_ ___m_

500

502

505

508

510

515

520

525

530

541

542

546

565

01

01

01

01

01

02

03

01

02

03

04

05

06

01

01

01

01

01

01

01

0.4445

0.4445

12131

0.6096

0.6096

0.6096

0.6096

0.9144

0.9144

.8288

1.8288

1.8288

12131

0.7180

0.7620

25.074

54.44

17.67

17.67

3.048

03063

2.212

1.2241

0.3626*

0.2970

02970

0.2970

0.2580

0.2580

02580

0.2580

02580

0306294

0.27871

1.5M

0.04635

0.06557

0.21677

0.21677

29.810

0.1362"

0.98320

1.4850

0.22107

0.1811*

0.1811"

0.18110

0.23590

0.2359*

0.47180

0.47180

0.4718"

0.3716"

0.2001*

1.21050

1.1622"

3.5696*

3.8303*

3.8303*

90.8609W

0.62450

1.6782"

1.9048

0.16397

0.10793

0.10793

0.10793

0.0234

0.0234

0.0234

0.0234

0.0234

0.5962

1.0827

0.64417

0.2429*

0.2889*

0.02

0.02

6.16080

0.444

OA44

-1.2131

-0.6096

-0.6096

-0.6096

-0.6096

03048

0.3048

0.6096

0.6096

0.6096

1.2131

0.718

0.762

0.0

0.0

0.0

0.0

0.0

5.1469

5.1469

3.4898

2.8802

2.2706

1.6610

1.0514

13562

1.6610

2.2706

2.8802

3.4998

4.7029

5.8649

6.5269

6.5269

6.5269

6.5269

6.5269

3.4898

SEPARATM

SNGLVOL

BRANCH

BRANCH

ANNULUS

PIPE

BRANCI

BRANCH

SNGLVOL

BRANCI

TMDPVOL

TMDPVOL

TMDPVOL

Pw sepato

-q ao bypass

S-pwo l d ou- volume

Fee WK upper doww.,mer

Stem generatmo downcomr

Stem gerator hoiter

Lower pat of steam dome

Upper part of stam dome

Stem line to MSCV

Steam line downstmem of MSCV

Air coled coodear

Steam bypas line

Feedwazer tank

563 01 3.048 29.810 90.8609* 6.6108" 0.0 3.4898 TMDPVOL IAwdliary kecdwaler tank
.~j5

0'

Table 5b Stem genetator secondary junction data

oxuP urn Volume number MAre Juntion LAM coeffiient Description

Num Num Prom To Flag Fowad Reverse

(m2) evca_ __

50w 01 50o0o0o 5200o0 0.3063 o01o00 037 037 Sepator team ofitke

02 5000000 5050000 0.14024 001000 0.0 0.0 Seprator liquid drain

03 5150100 5000000 0.29187 001000 4.404 4304 Sepaator entry from riser

505 01 5050100 5080000 03626* 000100 0.0 0.0 Liquid drain to downcomer

02 5050000 5020000 1.22410 000100 0.0 0.0 Comncdon to separ-tor bypass

508 01 5080100 5100000 0.2970 000100 0.0 0.0 Entry to downcomer

510 01 5100100 5100200 0.297 000000 0.0 0.0 Downoemer pipe junction

02 5100200 5100300 0.297 000000 0.0 0.0

513 00 5100100 5150000 0.258 000100 17.5 17.5 Downcomer to riser

515 01 5150100 5150200 0.258 000100 2.0 2.0 Steam generator riser junction

02 5150200 5150300 0.258 000100 2.0 2.0

03 5150300 5150400 0.258 000100 4.05 4.05

04 5150400 5150500 0.258 000100 4.05 4.05

05 5150500 5150600 0.258 000100 4.05 4.05

520 01 5200100 5250000 0.2787* 00100 0.0 0.0 Steam dome lower to upper

02 5020100 5200000 0.2787 000100 0.0 0.0 Sepamat bypass to steam dome

525 01 5250100 5300000 0.0464 000100 0.8 0.8 Steam exit to stem- line

540 00 5300100 5410000 0.003370 000110 0.0 0.0 Main steam control valve

541 01 5410100 5420000 0.065570 000100 0.0 0.0 Steam line outlet to condenser

545 00 5300100 5460000 0.00032 000110 0.0 0.0 Stm bypass valve

566 00 5650000 5080000 0.05 - 0.0 0.0 Feedwater inlet flow

569 00 5680000 5080000 0.05 0.0 0.0 Auxwliay feedwater Inlet flow
sIn

u1

Table 5c Steam generator secondary beat slab data

Heat Geometry Left Right Area/Lngth interval Material Left. Right

Stsucture Type Boundary Boundary /Factor Number Boundary Boundary

Number Volume Volume , (n2n/fiO) . (m) (m)

5000-001 CYL 50201 50001 0.85127 L 1 -4 C-Steel 0.3048 0.3143

0.8778 R

-002 51506 50501 2.51199 L

2.59028 R

5100-001 CYL 51505 50801 0.64635 1 -4 C-Steel 0.6445 0.6572

-002 51504 51001 2.46858 L

2.51723 R

-003 51503 51002 2.46858 L

2.51723 R

-004 51502 51003 1.23429 L

1.25862 R

-005 51501 51003 1.23429 L

1.25862 R

5250-001 CYL 52501 0 0.76238 1 - 5 C-Steel 0.7112 0.76397

-002 52001 .0 0.7520

-003 50001 0 0.4445

-004 50501 0 1.2131

-005 50801 0 0.6096

-006 51001 0 0.6096

-007 51002 0 0.6096

-008 51003 0 0.6096

I
9~

Mi

W'

Table 6a ECC Systems volume data

Comp Vol Length Area Volume Hyd PLev PMev COMP Description

Num Nmn Dimn Change Oulet Type

(M) (m2) (m3) (M) (M) (M)

605 01 5.0148 0.00599 0.03003* 0.0873* 3.307 0.0 SNGLVOL ECCS header

615 01 25.9972 0.01567* 0.4075 0.14130 0.0 -3.307 SNGLVOL Accumulator pipe

620 01 3.0393 1.2485* 3.7946 1.2608" 3.0393 0.1803 ACCUM Accumulator tank

3.3226 0.01864 0.06193 0.281" 0.448 -2.859 Accumnlator standpipe and line

625 01 5.0 20.44 102.2" 5.1015' 5.0 -3.307 TMDPVOL Borated water storage tank LPI

Indicates input as 0.0 and value calculated by code.

Ir~

(hi
W.

U'

Table 6b ECC Systs junction data

Camp Jun Volume number Area Junction Loss coefficient Description

Num Num From To Flag Forward Reverse

(012) evcahs

600 00 6050100 1850000 0.00599* 001110 0.935 0.935 ECCS control valve

610 00 6150100 6050000 0.00599* 001000 6.278 6.278 Accumulator valve

630 00 6250000 6050000 0.00599* 000000 0.0 0.0 LPIS junction from BWST

640 00 6250000 6050000 0.00599* 000000 0.0 0.0 HPIS junction from BWST

0.0" Indicates input as 0.0 and value calculated by code.

I

I
Steam outlet

to Secondary coolant system (figure

Inlet to secondary

coolant system (figure 6)

"ECC cold leg

Injection

(figure 7)

INEL-A.15 148

Figure 1. LOFT System--intact loop.

AEEW-R 2454 -45-
€• •N 23

0tt 

- 37.44 - -32.56-1

1 ii

. seeoaawm Tnk CV-P-136-71 - CV-P-13-/-70

" Hood"

-o-nt 

F 

a 

..

PLA 14A9.S'

F g r2v-:PLOFT Sr

slo"rammolr FF-P-138-9 160 otw

4LA 14- . V I,,

F41.re 2 LOF - roe4Lo 0'te 
Hot

leg

<,A

Intact loop

hot leg

0.

Intact lool

cold leg <\A

Cold

leg

'Inlet annulus

- Upper

Plenum

-Downcomer

-'Core

Lower plenum

270"

SECTION AA INEL-A.15 153-1

Figure 3. LOFT System--reactor vessel.

AEEW-R 2454 -47-
Spray inlet line

Pressure relief

line

INEL-A.15 151

Figure 4. LOFT System--pressurizer.

AEEW-R 2454 -48-
-Steam outlet

~-Perforated plate

M, Mist extractor

Mist extractor drain

Feedwater Inlet -. 6L

Steam water mixture

Downcomer

- Primary separator

- Support skirt

Baffles

-Primary inlet

Manway drain

INEL.A.15 150

Primary

Figure 5. LOFT System--steam generator.

-49- AEEW-R 2454
SCS steam flow

L•Air cooled condenser

Steam

valve.

to steam

generator

.. ,I

I *I.

'" I --

Secondary coolant -. i I

circulating pump

INEL-A.15 152

Figure 6. LOFT System--secondary side.

AEEW-R 2454 -so-
U'

M'

Borated water

line

discharge

cold leg Containment vessel

Acc. discharge

Isolation valve

-Containment vessel

floor

Reactor vessel

pump ECC-P-64A

LPIS heat exchanger

INEL-A-15 154

Figure 7. LOFT System--ECC.
Lii

.Ib

M10

7

5

4

3

2

I

103

515

315

116

350

a

4

3

2

23O

Figure 8 - RELAPS/MOD2 Noding for LOFT Calculations
9

U1

WN

iYYY

zzz

A

Fluid volume - XXX

Junction - YYY

Heat structure - ZZZ

Crossflow junction

Volume A Is crossflow

Valve

Pump

U'

Ia

Figure 9 - Key to noding symbols
ulj

Hot Leg

SG Primary Break

E D

I I

SG Inlet

SG Outlet Plenum Hot Leg

Plenum

Pump Discharge

Lines and Tee

A

B

I

U1

ECC

Valve C

Crossover

Leg

Cold ECC

Header

> Pump Injection

Accumulator Une

and Tank

BWST

Pump

Inlet

Pump Suction

Une and Tee

Figure 10 a Intact loop - description of components
9'

U'

lob

116

A

B

118

I

I

Figure 10 b Intact loop - noding of components
L'

60-6

.7

-8

-9

60-10

1004-2 A

B

I'

1004-3

1001-6

Figure 10 c Intact loop - noding of heat slabs
g 3.341

ti'

2.880

2.271 --

u' 1.661

01.356-.*.

0.759 - -

0.246

U'

-2.252_*

-0.941

- -1.297•

-1.297

Figure 10 d Intact loop - volume outlet elevations
Inlet annulus

upper

A

B

middle

C

lower

Downcomer

Filler gap -

Upper plenum top

Upper plenum middle

bottom

.9-G

Dead end fuel modules

Flow skirt

Upper support X-flow

Upper end box /

support

Lower core support

Lower plenumr

upper

Lower plenum

lower

Figure 11 a Reactor Vessel - description of components

AEEW-R 2454 -58-
A

B F

I~ I )

223 -1 -1

240

-21

-2 ............. -3 -6 -3 .1 ....... -5

-4

-4 -2 ................

-3

-3 "5 -1 1 .............. -2

-1

235 230

-6 225

215

-4 1220

Figure 11 b Reactor vessel -noding of components

AEEW-R 2454 -59-
Core support

barrel

Filler blocks

Upper plenum

Internals

A

B -+

C

Vessel wall -•

Core support

barrel

Fuel modules

(top)

Flow skirt/

core filler

Fuel rods

Lower core

support

Filler

Figure 1 Ic Reactor vessel - description of heat slabs

AEEW-R 2454 -60-
2601 2602

Figure 11 d Reactor vessel - numbering of heat slabs

AEEW-R 2454 -61-
0.330

A

B

0.143

C

0.0

-0.424 - "•

-4.256 - --

Figure 11 e Reactor vessel - volume outlet elevations

AEEW-R 2454 •-62-
9J

RV nozzle

BLHL

BLHL to

RABL tee

RABL tee/

BLHL contraction

Pipe to isloation

valve

I~

CbJ

F

RABL valve

G

RV nozzle

BLCL

6LCL to

RABL tee

RABL tee/

BLCL contraction

Pipe to Isloation

valve

Figure 12 a Broken loop (without simulators) - description of components
U'

ur~.

300 305 310 315-1 315-2

F

I~

375

G

335 340 345 350-1 350-2

Figure 12 b Broken loop (without simulators) noding of components
U1

3000-1 3000-2 3000-3 3151-1 3152-1

F

U'

G

3350-1 3350-2 3350-3 3501 3502

Figure 12 c Broken loop (without simulators) - noding of heat slabs
lob.

0.0 0.0 0.0

F

I

0I

G

0.0 0.0 0.0 0.0 0.0

Figure 12 d Broken loop (without simulators) - volume outlet elevations
Lfl

SG simulator

Pump simulator

RV nozzle BLHL to RABL tee/

BLHL RABL tee BLHL contraction

F

O•I

'•1

I

RABL hot leg side Line to

Islation

RABL valve valve

RABL cold leg side

G

RV nozzle

BLCL

BLCL to

RABL tee

RABL tee/ Pipe to isloation

BLCL contraction valve

Figure 12 e Broken loop (with simulators) - description of components
9%

W'

-6 -5

-4

-3

-2

315-1

-7

-8

-9

300 305 310 315-12

F

380

ODI0

I 375

G

335 340 345 350-1 350-2

Figure 12 f Broken loop (with simulators) noding of components
U'j

-5

-4

-3

-2

3151-1

-6

-7

-8

-9 3151-12

3000-1 3000-2 3000-3

F"

I%

G

3350-2 3350-3 3501 3502

Figure 12 g Broken loop (with simulators) - noding of heat slabs
3.124

2.667 0 .--- - U' Ln

1.673

0.679 -•

0.0 0.0 0.0 0.127 0.0 0.0

F

I4

0,,

G

0.0 0.0 0.0 0.0 0.0

Figure 12 h Broken loop (with simulators) - volume outlet elevations
Gontarinment

I

Dummy volume SRV

and valve (for

Initialisation) PORV

Prressudser top

Spray valve

.Pressuriser

vessel

Spray line

Pressuriser

surge line

D E

Figure 13 a Pressuriser system - description of components

AEEW-R 2454 -71-
805

450 455

420

415

405

440 400

Figure 13 b Pressuriser system - noding of components

AEEW-R 2454 -72-
4201-1

4153-2

4153-1

4152-6

-5

-4

-3

-2

4152-1

D E

Figure 13 c Pressuriser system - noding of heat slabs

AEEW-R 2454 -73-
3.093-- 3.093

2.991

................ 2.796

............. 2.400

....... ft.......... 1.871

.................. . 1.474

1.322

1.140

.... .0.840

0.540

D E

Figure 13 d Pressuriser system - volume outlet elevations

AEEW-R 2454 -74-
Steam bypass

valve

Steam bypass

line

UI

Steamline

to MSCV

Steam dome

-upper

Steam dome

-lower

Primary separator

MSCV Steamline

from MSCV

Separator bypass

Separator

liquid outlet

Condenser

Feedwater tanks

Main

Auxiliary

u1 -4

Feedwater inlet

upper downcomer Boiler

Downcomer

Figure 14 a Secondary system - description of components
ul

-4

0'

545

566

515 510

513

Figure 14 b Secondary system - noding of components
U'

525-1

525-2 5MI 525-3

I I

' / 500-2 III525-

-rn 525-5

510 -1

F-2 ....... 525-6

-2-

F -5 14

Figure 14 c Secondary system - nocring of heat slabs
6.527

U'

I

6.257

5.865

5.147

4.703

3.490

2.880

2.271

1.661

1.356

3.490

2.271

1.661

1.051

Figure 14 d Secondary system - volume outlet elevations
DISTRIBUTION

WINFRITH TECHNOLOGY CENTRE, DORCHESTER, DORSET, DT2 SDH

Mr A 7 Briggs

Dr A T D Butland

Dr I H Gibson

Dr J C Birchley

Mr A J Smethurst

Mr1G JWard

Dr S Kinnersly

Mr I Sherwin

Mr I Brittain

Dr C G Richards

Mr R O'Mahoney

Mrs S Newbon

Dr W M Bryce

226/B21

343/B41

236/A32

(4) 230/A32

234IA32

239/A32

203/A32

245/A32

201/A32

260/A32

263/A32

232/A32

262/A32

Mr J Fell 1 Melstock Avenue, Dorcheter, Dorset

NUCLEAR ELECTRIC, BARNETT WAY, BARNWOOD, GLOUCESTER, GL4 7RS

Mr N A J Bun

Mr I L Hirst

Mr P C Hall

Dr K H Ardron

NUCLEAR ELECTRIC, BERKELEY NUCLEAR LABORATORIES, BERKELEY, GLOUCESTER, GL13 9PB

Dr I Young

NUCLEAR POWER TECHNOLOGY AND ENVIRONMENT CENTRE, KELVIN AVENUE,

LEATHERHEAD, SURREY

I& M W E Coney

Dr J Putney

NUCLEAR ELECTRIC, MARCHWOOD ENGINEERING LABORATORIES, SOUTHAMPTON, S04 4ZB

Mr B Chojnowski

AEEW-R 2454
INFORMATION TECHNOLOGY DIRECTORATE, 85 PARK STREET, LONDON, SEl

Mr L Wilson

Mr 0 France

NUCLEAR ELECTRIC, LAUD HOUSE, 18 WARWICK LANE, LONDON, EC4 4EB

Mr I R Harrison

Dr P R Farmer

Mr A L Willetts

Dr F Evans

NUCLEAR ELECTRIC, PWR PROJECTS GROUP, BOOTHS HALL, CHELFORD ROAD,

KNUTSFORD, CHESHIRE, WA16 8QZ

Mr P Chappall

Mr P Lightfoot

UKAEA, SAFETY AND RERLIABILITY DIRECTORATE, WIGSHAW LANE, CULCHETH,

WARRINGTON, CHESHIRE,

Mr J G Moore

Mr R Cox

UKAEA, C35, 329, AERE HARWELL, OXFORDSHIRE, OX1l ORA

Dr D Hicks

Dr G F Hewitt

SOUTH OF SCOTLAND ELECTRICITY BOARD, CATHCART HOUSE, INVERLAIR AVENUE, GLASGOW, SCOTLAND

Mr J R P Eaton

NATIONAL NUCLEAR CORPORATION, BOOTHS HALL, CHELFORD ROAD, KNUTS.

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NRC FORM 335 US. NUCLEAR REGULATORY COMMISSION 1. REPORT NUMBER

(2-89) (AdNuled by NRC. Add Vol, Suisp Rev.. NRCM 1102. DT Addend Numb• If any.) 3201.3202 BIBLIOGRAPHIC DATA SHEET NUREG/IA-0072

(See instructions on the reverse) AEEW-R2454

2. TITLE AND SUBTITLE

LOFT Input Dataset Reference Document for

RELAP5 Validation Studies 3. DATE REPORT PUBLISHED

April. 1992

4. FIN OR GRANT NUMBER

A4682

5. AUTHORIS) 6. TYPE OF REPORT

J. C. Birchley Technical

7. PERIOD COVERED Ilncusi.e Dates)

&. PERFORMING ORGANIZATION - NAME AND ADDRESS Wf NRC. provide Division, OfficeaorRagion, U.S NuckdeReeguiarory Common. and malin address; if fcntractor, provide

nanve and mailing address.)

Winfrith Technology Centre

United Kingdom Atomic Energy Authority

Dorchester, Dorset, DT2 8DH

United Kingdom

9. SPONSORING ORGANIZATION - NAME AND ADDRESS (If NRC, type -w as abovre"; if contrmctor, provide NRC ODision. Office or Reg;on, U.S. Nuclear Regularoy Conomisio,

and mailingt address.I

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, DC 20555

10. SUPPLEMENTARY NOTES

11. ABSTRACT (200 words ar ss)

Analyses of LOFT experiment data are being carried out in order to validate the RELAP5

computer code for future application to PWR plant analysis. The MODI dataset was also

used by CEGB Barnwood who subsequently converted the dataset to run with MOD2. The

modificationsincluded changes to the nodalisation to take advantage of the crossflow

junction option at appropriate-locations. Additional pipework representation was

introduced for breaks in the intact (or active) loop. Further changes have been made

by Winfrith following discussion of calculations performed by the CEGB and Winfrith.

These concern the degree of noding in the steam generator, the fluid volume of the stearr

generator downcomer, and the location of the reactor vessel downcomer bypass path.

This document describes the dataset contents relating to the volume, junction, and heat

slab data for the intact loop, reactor pressure vessel, broken loop, steam generator

secondary, and ECC system. Also described are the control system for steady state

initialization, standard trip settings and boundary conditions.

12. KEY WORDS/DESCRIPTORS (List woo orphraes that will asesst reseachert In locating the report.) 13. AVAILABILITY STATEMENT

Unl imi ted

LOFT, RELAP5, Validation Studies 14. SECURITY CLASSIFICATION

(This Peer

Unclassified

(This 01R4por)

Unclassified

15. NUMBER OF PAGES

16. PRICE

NRC FORM 335(249)


THIS DOCUMENT WAS PRINTED USING RECYCLED PAPER

NUREG/IA-0072 LOFT INPUT DATASET REFERENCE DOCUMENT FOR RELAP5 VALIDATION STUDIES APRIL 1992

UNITED STATES

NUCLEAR REGULATORY COMMISSION

WASHINGTON, D.C. 20555

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POSTAGE AND FEES PAID

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