NUREG/IA-0202

International 

Agreement Report 

Analyses of KS Test Data on the Heated 

Rod Bundle Temperature Behavior in 

RBMK-1500 Core Model Under Stop and 

Recovery Flow Using RELAP5/MOD3.2 

and RELAP5/MOD3.2.2 GAMMA 

Prepared by 

V.A. Vinogradov, A.Y. Balykin 

Nuclear Reactor Institute, Russian Research Center 

Kurchatov Institute 

Kurchatov Square 1 

123182, Moscow Russia 

Office of Nuclear Regulatory Research 

U.S. Nuclear Regulatory Commission 

Washington, DC 20555-0001 

April 2001 

Prepared as part of 

The Agreement on Research Participation and Technical Exchange 

under the International Code Application and Maintenance Program (CAMP) 

Published by 

U.S. Nuclear Regulatory Commission
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NUREG/IA-0202

International 

Agreement Report 

Analyses of KS Test Data on the Heated 

Rod Bundle Temperature Behavior in 

RBMK-1500 Core Model Under Stop and 

Recovery Flow Using RELAP5/MOD3.2 

and RELAP5/MOD3.2.2 GAMMA 

Prepared by 

V.A. Vinogradov, A.Y. Balykin 

Nuclear Reactor Institute, Russian Research Center 

Kurchatov Institute 

Kurchatov Square 1 

123182, Moscow Russia 

Office of Nuclear Regulatory Research 

U.S. Nuclear Regulatory Commission 

Washington, DC 20555-0001 

April 2001 

Prepared as part of 

The Agreement on Research Participation and Technical Exchange 

under the International Code Application and Maintenance Program (CAMP) 

Published by 

U.S. Nuclear Regulatory Commission
ABSTRACT

This report has been prepared as a part of the Agreement on Research Participation and 

Technical Exchange under the International Code Application and Maintenance Program. 

KS experimental data on the behavior of the heated rod bundle temperature in the RBMK

1500 core model under stop and recovery flow conditions were simulated with 

RELAP5/MOD3.2 and RELAP5/MOD3.2.2GAMMA to assess the codes suitability. 

Especially calculations were performed to estimate differences in the code version predictions 

for processes/phenomena, which could occur under specific conditions of RBMK type reactor 

during LOCA with MCP's pressure header rupture and subsequent ECCS water injection. 

This problem addresses phenomena of high importance to RBMK-1500 safety including 

water discharge, critical heat flux, post dryout heat transfer, reflood and propagation of 

rewetting front in the fuel channel during an accident. 

The test have been carried out at KS semi-integral test facility (Russian Research Center 

Kurchatov Institute) represented RBMK primary circuit. The main purpose of the experiment 

was investigation of temperature conditions in the fuel assembly under high power value, inlet 

flow rate being decreased drastically up to complete stop of the flow followed by pressure 

header rupture. A subsequent flow rate resumption was also assumed, the fuel assembly 

power high level being unchanged. 

First a study of the effect of the hydraulic nodalization to the code calculations was performed 

using different number of hydraulic volumes for the fuel channel model. After the choice of 

proper nodalization and maximum user-specified time step, base case calculations were done 

for the test. 

Sensitivity studies were carried out to investigate the effects of modeling on the behavior of 

the rod simulator temperatures along the height of the fuel assembly model.

iii
TABLE OF CONTENTS 

1. INTRODUCTION 1 

1.1. Objectives 1 

1.2. Background 1 

1.3. Study Description 1 

1.4. Report Organization 2 

2. DESCRIPTION OF RBMK LOOP MODEL ON KS TEST FACILITY 3 

3. DESCRIPON OF THE TEST 6 

4. DESCRIPTIONS OF RELAP5 MODEL AND BASE CASE INPUT DECKS FOR 

THE TEST 10 

4.1. RELAP5/MOD3.2 Model and Assumptions 10 

4.1.1. Main allowances for simulation of the test 10 

4.1.2. KS RBMK MFCC model nodalization and input data description 10 

4.1.3. Methods of computer modeling of the experiment 15 

4.2. RELAP5/MOD3.2.2 GAMMA Model and Assumptions 16 

5. RESULTS OF THE CODES ASSESSMENT 17 

5.1. RELAP5/MOD3.2 Base Case Resttlts, Comparisons to KS Test Data and 

Conclusions 17 

5.2. RELAP5/MOD3.2.2 GAMMA Base Case Results, Comparisons to KS Test 

Data and Conclusions 22 

6. SENSITIVITY STUDY 25 

7. RUN STATISTICS 26 

8. SUMMARY OF CONCLUSIONS 27 

REFERENCES 28 

Appendix- A: Original Date Plots from KS Test 5 A-1 

Appendix- B : RELAP5/MOD3.2 Base Case Results B-1 

Appendix- C : RELAP5/MOD3.2.2 GAMMA Base Case Results C-1

V
Appendix- D: Sensitivity Study Results D-1 

Appendix- E Base Case RELAP5/MOD3.2 Input Deck Listing E-1 

LIST OF FIGURES 

Fig.2. 1. KS RBMK MFCC model 4 

Fig. 2.2. Fuel channel model cross section 5 

Fig. 2.3. Cable thermocouple placement into the wall of the fuel rod simulator 5 

Fig. 3.1. Measurements scheme 9 

Fig. 4.1. Nodalization scheme of the RBMK MFCC model at the KS test facility 11 

Fig. 4.2. Nodalization scheme of the RBMK-1500 Fuel channel model. 13 

Fig. 7.1. Execution time (CPU TIME) of the main variant computation for the 

experiment 26 

Fig. 7.2. Integration step (dt) variations at the main variant computation for the 

experiment 27 

Fig. A-1. Mass flow rate G history at the FC model inlet in experiment 5. A-2 

Fig.A-2. Pressure drop DP16-4 history along the FA model in experiment 5 A-2 

Fig. A-3. Pressure Pin history in the lower part of the FA model in experiment 5 A-3 

Fig. A-4. Fuel rod simulator temperature Twl (z=6.894 m) history in experiment 5 A-3 

Fig. A-5. Fuel rod simulator temperature Tw2 (z=6.854 m) history in experiment 5 A-4 

Fig. A-6. Fuel rod simulator temperature Tw3 (z=3.814 m) history in experiment 5 A-4 

Fig. A-7. Fuel rod simulator temperature Tw4 (z=1.044 m) history in experiment 5 A-5 

Fig. A-8. Behavior of measured wall temperatures Twl, Tw2, Tw3 and Tw4 in 

experiment 5 A-6 

Fig. B-1. Mass flow rate G (t) history at the FC model inlet B-2 

Fig. B-2. Coolant temperature Tin (t) history at the FC model inlet B-2 

Fig. B-3. Pressure Pin (t) history in the lower part of the FA model B-3 

Fig. B-4. Pressure drop DP16-4 (t) history along the FA model B-3 

Fig. B-5. Fuel rod simulator temperature Twl (t) history B-4 

Fig. B-6. Fuel rod simulator temperature Tw2 (t) history B-4 

Fig. B-7. Fuel rod simulator temperature Tw3 (t) history B-5 

Fig. B-8. Fuel rod simulator temperature Tw4 (t) history B-5

vi
Fig. C-1. Comparisons between test data and RELAP5/MOD3.2 and 

RELAP5/MOD3.2.2GAMMA predictions for the behaviors of the considered 

parameter G and rod's wall temperatures Twl-Tw4 in the base case with "motor 

valve 2r" C-2 

Fig. C-2. Comparisons between test data and RELAP5/MOD3.2 and 

RELAP5/MOD3.2.2GAMMA predictions for the behaviors of the considered 

parameters Pin and DP16-4 in the base case with "motor valve 2r" C-3 

Fig. C-3. Comparisons between test data and RELAP5/MOD3.2 and 

RELAP5IMOD3.2.2 GAMMA predictions for the behaviors of the rod's wall 

temperatures TwI and Tw2 in the base case with "motor valve 2r" C-4 

Fig. C-4. Comparisons between test data and RELAP5/MOD3.2 and 

RELAP5IMOD3.2.2GAMMA predictions for the behaviors of the rod's wall 

temperatures Tw3 and Tw4 in the base case with "motor valve 2r". C-5 

Fig. C-5. Comparisons between test data and RELAP5/MOD3.2 and 

RELAP5/MOD3.2.2GAMMA predictions for the behaviors of the rod's wall 

temperatures Twl - Tw4 in the base case with "motor valve 2r" C-6 

Fig. D-1. Comparisons between test data and RELAP5/MOD3.2.2GAMMA 

predictions for the behaviors of the considered parameters G and P in the cases with 

"motor valve 2r" and Time Dependent Junction in LWC D-2 

Fig. D-2. Comparisons between test data and RELAP5/MOD3.2.2GAMMA 

predictions for the behaviors of the considered parameters DP16-4 and Twl in the 

cases with "motor valve 2r" and Time Dependent Junction in LWC D-3 

Fig. D-3. Comparisons between test data and RELAP5JMOD3.2.2GAMMA 

predictions for the behaviors of the rod's wall temperatures Tw2 and Tw3 in the cases 

with "motor valve 2r" and Time Dependent Junction in LWC D-4 

Fig. D-4. Comparisons between test data and RELAP5IMOD3.2.2GAMMA 

predictions for the behaviors of the rod's wall temperatures Tw4 and Twl-Tw4 in the 

cases with "motor valve 2r" and Time Dependent Junction in LWC D-5

vii
LIST OF TABLES 

Table 3.1. Parameters of the initial steady state for KS RBMK-1500 Test 5. 6 

Table 3.2. List of measured parameters and measurement errors 8 

Table 4.1. The alignment of the nodalization in the fuel channel with the grid spacers 12 

Table 5.1. Comparison of the base case calculated, sensitivity studied and 

experimental values of the main mode parameters at the steady state 18 

Table 5.2. The results of RELAP5/MOD3.2 code assessment (code performance for 

process/phenomenon) 21 

Table 5.3. The results of RELAP5IMOD3.2.2 GAMMA code assessment (code 

performance for process/phenomenon) 24

viii
EXECUTIVE SUMMARY

Analyses of KS test with stop and recovery flow in the RBMK-1500 core model are presented in 

the Report. The objective of the analyses is to assess the RELAP5/MOD3.2 and 

RELAP5/MOD3.2.2 GAMMA codes for covering thermal and hydrodynamic processes in RBMK 

type reactor under MCP's pressure header large break conditions. Especially calculations were 

performed to estimate differences in the code version predictions for phenomena/processes, which 

could occur during LOCA. This problem addresses phenomena of high importance to RBMK-1500 

safety including water discharge, critical heat flux, post dryout heat transfer, reflood and 

propagation of rewetting front in the fuel channel during an accident. 

The test have been carried out at the KS semi-integral test facility (RRC KI) represented RBMK 

primary circuit. The main purpose of the experiment was investigation of temperature conditions in 

the fuel assembly under high power value, inlet flow rate being decreased drastically up to complete 

stop of the flow followed pressure header rupture. A subsequent flow rate resumption was also 

assumed, the FA power high level being unchanged. 

Full scale model of one fuel channel with RBMK-1500 fuel assembly was used in the test. An 

abrupt flow rate termination with a high FA power level conserving attributed to the emergency 

under consideration was modeled by the FC inlet valve closure. The flow rate was recovered as the 

heated rod temperature reached the limit value. To do this the FC inlet valve was opened. It was the 

way to simulate the ECCS water supply into the fuel channel. FA model power, FA inlet pressure, 

FC inlet flow rate and coolant temperature, pressure drop across the FC section with heated rod 

bundle, heated rod temperatures along the FA model were recorded during the test. 

The models of RELAP5IMOD3.2 and RELAP5/MOD3.2.2 GAMMA codes were investigated. 

Special emphases were given to the codes performance for the following processes/phenomena: 

"* Pressure drop and water release from the fuel channel model and rod bundle surface drying. 

"* Dryout under sharp flow deceleration at the inlet of the RBMK-1500 fuel assembly model. 

"* Post dryout heat transfer and heated rod's wall temperature behavior in the fuel assembly model 

under channel drying. 

* Propagation of the reflood and quench fronts in the fuel assembly model under water flow 

resumption at the channel inlet. 

First a study of the effect of the hydraulic nodalization to the code results was performed using 

different number of hydraulic volumes for the fuel channel model. After the choice of proper

ix
nodalization with 40 nodes for the FA channel and maximum user-specified time step dtmax=0.01 

s, the base case calculations were done for the test. 

Sensitivity studies were carried out to investigate the effects of modeling on the behaviors of the 

rod simulator temperatures along the heated bundle height using motor valve component or Time 

Dependent Junction in LWC. Use of TDJ to accurate code simulation of the real flow rate behavior 

at the channel inlet gives more realistic code results for the initial and boundary conditions in the 

fuel channel. In this case the code predicted time interval Atd from the moment t(GO) of complete 

stop flow to the beginning td of the rod's wall temperature Twl(t) increase at the core outlet exceeds 

the experimental value Atd by about - 0.2 s. This indicates a reasonable adequacy of the code 

simulation of dryout initiation at' rapid decrease of the coolant flow right down to its total 

termination. Also, sensitivity studies were performed with estimating what was the influence of 

various models applied in these codes on calculation accuracy. 

Code results are presented as time-dependent curves: - pressure Pin (t) in the lower part of the 

heated rod bundle, coolant temperature Tin (t) and mass flow rate G (t) at the FC model inlet, total 

pressure drop DP16-4 (t) across the heated bundle height, heated rod temperatures Twl (t), Tw2 (t), 

Tw3 (t), Tw4 (t) along the FA model height. 

The curves serve for comparison of the calculation results with test data to appreciate codes 

suitability. 

* Comparison of RELAP5/MOD3.2 results allow to draw a conclusion on reasonable agreements of 

general pictures of simulated processes/phenomena with test data on the stage with the decrease and 

complete stop of flow. 

At the same time, it was intimated that there is a need to modify RELAP5/MOD3.2 models used for 

interphase friction and critical heat flux in the channel with the RBMK-1500 fuel assembly under 

initial steady conditions with forced circulation. 

* When simulating the recovery stage of water supply into the channel there were essential 

distinctions between RELAP5/MOD3.2 code results and test data on the behaviors of the rod wall 

temperatures along the FA height. The code does not give qualitative agreement between the curves 

for the rod temperatures along the FA height at the quenching in the test. The code gives 

insufficient agreements with test data concerning the time characteristics and conditions of the rod 

surface quenching in the upper and middle parts of the FA. The analysis results allow the code 

suitability being assessed as insufficient. This stems from the fact that RELAP5/MOD3.2 reflood

x
model has not been adequately worked through and the developers do not recommend it to use. 

Shown is a necessity and importance of a special reflood model to be used for suitable description 

of the reflood stage of the transient. At assessment of the advanced code version 

RELAP5/MOD3.2.2 GAMMA and its reflood model, it is necessary to achieve a suitable 

simulation of the initial conditions for the recovery stage of water supply into the channel during 

the transient. 

* Comparison RELAP5/MOD3.2.2 GAMMA results allow to draw a conclusion on a reasonable 

agreement of general pictures for simulated processes/phenomena with test data on the stage of the 

decrease and complete stop of flow. 

RELAP5/MOD3.2.2 GAMMA results obtained when simulating reflood and quench fronts in the 

fuel cannel allow the code adequacy being assessed as reasonable for the upper part of RBMK-1500 

fuel assembly and as insufficient for the lower part of the FA model. 

o Shown is a necessity for formulation special Standard Problem "Propagation of the reflood and 

quench fronts in the lower and upper parts of the RBMK-1500 fuel assembly under flow resumption 

at the channel inlet" and its analysis using RELAP5/MOD3.2.2 GAMMA.

xi
NOMENCLATURE

N - electrical power of the FA model, kW; 

G - water flow rate at the fuel channel inlet, kg/s; 

Pin - pressure in the sampling point 15 of the fuel channel model, MPa, bar; 

DPI 6-4 - actual pressure drop between the pressure taps 16 and 4, Pa; 

Tin - water temperature at the fuel channel inlet, K; 

TwI - Tw4 - rod fuel simulator wall temperature, K; 

RRC KI - Russian Research Centre "Kurchatov Institute" 

LWC - lower water communication lines; 

SWC - steam-vapor water pipelines; 

GDH - group distribution header; 

ICV - isolating-control valve; 

MFCC- multiple forced circulation circuit; 

MCP - main circulation pump; 

DS - drum-separator; 

DM - differential manometer; 

ECCS - emergency core cooling system; 

PH - pressure header; 

FE - fuel element; 

FA - fuel assembly; 

FC - fuel channel; 

TDJ - Time Dependent Junction; 

exp - experimental value; 

calc - calculated value.

xii
1. INTRODUCTION

1.1. Objectives 

The main goals of this work are: 

- Analyses of the KS experimental data on the behavior of the heated rod temperatures in the 

RBMK-1500 core model under stop and recovery flow conditions using RELAP5/MOD3.2 and 

RELAP5/MOD3.2.2 GAMMA; 

- Assessment of the codes suitability for description of thermal and hydraulic processes, which 

could occur under specific conditions of RBMK-1500 type reactor during an accident with MCP's 

pressure header rupture and subsequent ECCS water injection. 

Especially calculations were performed to estimate differences in the code version predictions for 

phenomena/processes, which could occur during LOCA. This problem addresses phenomena of 

high importance to RBMK-1500 safety including water discharge, critical heat flux, post dryout 

heat transfer, reflood and propagation of rewetting front in the fuel channel during an accident. 

1.2. Background 

To help ensure RELAP5 code can be used with confidence, Russian Research Centre "Kurchatov 

Institute" has agreed to perform and document independent assessment of the code for a wide range 

of applications. These exercises are necessary to help identify and quantify any code shortcoming, 

in particular for the Russian types of reactors VVER and RBMK. This report has been prepared as a 

part of the Agreement on Research Participation and Technical Exchange under the International 

Code Application and Maintenance Program. Analyses of KS Test 5 with RBMK-1500 core model 

under stop and recovery flow conditions were performed using the latest versions of the codes 

RELAP5/MOD3.2 and RELAP5/MOD3.2.2 GAMMA. 

1.3. Study Description 

MCP's pressure header break is one of the design basis accidents in RBMK type reactor. KS 

RBMK MFCC model is semi-integral model of RBMK primary system for investigations 

hydrodynamics and heat transfer under normal and accident conditions of a reactor. In this facility 

series of the tests with RBMK-1500 core model under stop and recovery flow conditions were 

performed at Russian Research Centre "Kurchatov Institute" during 1977 year [1]. 

The aim of the chosen KS RBMK-1500 Test 5 was to investigate temperature mode of the fuel 

assembly under sharp decrease in coolant flow rate right down to its total termination and its

I
recovery at constant high FA power generation. A similar situation can take place in the FC of the 

reference RBMK when MCP's pressure header breaking. In this case all the group distribution 

headers connected to the pressure header are cut off by the check valves, which are installed at the 

inlet to these group headers. Water ceases to be delivered into the fuel channels. There begins steam 

filling in the channels. To prevent FA overheating, ECCS water is supplied into the core. 

Phenomena of hydrodynamics and heat transfer in RBMK-1500 core under MCP's pressure header 

break conditions are specific. So, it is necessary to estimate adequacy of the models of the code 

versions for modeling of these phenomena, because there are specific features in design of the core 

and fuel assembly of RBMK-1500. These specific features are FA rod location, geometry of rod 

and FA elements, hydraulic diameters of rod bundle cells and number of space grids, which are 

equipped with heat exchange intensifiers in the FA upper part. The behaviors of the core pressure 

drop and temperatures of the rods directly depends on these factors during LOCA. 

The code simulation results are presented as curves. Pressure at the inlet of the FC model with FA, 

coolant temperature and mass flow rate at the FC model inlet, total pressure drop across the FA 

height and rod simulator temperature along FA have been plotted as time-dependent parameters for 

the experiment. The curves serve for comparisons of calculation results with experimental data to 

appreciate code suitability. The differences between RELAP5/MOD3.2 and RELAP5/MOD3.2.2 

GAMMA predictions for the behaviors of the rod simulator temperatures along the height of the FA 

model and test data are described and analyzed. 

Sensitivity studies were performed to investigate the influence of various process/phenomenon 

models applied in the code on calculation accuracy as well as nodalization and integration time step. 

1.4. Report Organization 

The following sections present and describe the steps that were taken to facilitate the codes 

assessments. In Section 2 the RBMK MFCC model at the KS Test Facility is described, and KS 

RBMK-1500 Test 5 is described in Section 3. Descriptions of RELAP5 model and base case input 

decks for the test modeling are given in Section 4. The base case results of the codes simulations for 

the test, comparisons of the calculated and measured values and conclusions are presented in 

Section 5. Sensitivity studies results are presented in Section 6, and run statistics are given in 

Section 7. In Section 8 summary of conclusions is presented. In the Appendix E one finds the base 

case RELAP5IMOD3.2 input deck listing for KS RBMK-1500 Test 5.

2
2. DESCRIPTION OF RBMK LOOP MODEL ON KS TEST FACILITY

The KS test facility simulates the main forced circulation loop of RBMK primary circuit. 

KS RBMK MFCC model (Fig. 2.1) includes models of all the main elements of RBMK multiple 

forced circulation circuit: - (1) pressure header (PH), (2) group distribution header (DH), (3) lower 

water communication lines (LWC), (4) an isolating control valve (ICV), (5) a full-size fuel channel 

(FC) with (6) an electrically heated fuel assembly (FA), (7) the lifting path with (8) assembly 

suspension, and (9) steam water communication lines (SWC). The SWC horizontal section has a 

slope of 0.7 o. The upper horizontal header (10) and three vertical separators (11) do not model real 

drum separators (DS) but provide boundary conditions in the circuit outlet. 

The model of RBMK-1500 fuel assembly (Fig. 2.2) includes 18 fuel element simulators made of 

stainless steel tubes of 13.5 mm OD and a central unheated rod (OD 15 mm) of the same steel. The 

radial power peaking in the fuel assembly is provided due to differences in wall thickness of the 

heated tubes: wall thickness of 12 tubes in the peripheral row is 4 mm and that of 6 tubes in the 

inner row is 3 mm. The FE power in the peripheral row is higher than that in the inner row being 

proportional to the ratio of cross section arias of FE simulator tube walls (- 1.21), and it correlates 

as 1.061 to 0.878, if 1 is the average FE's power. The fuel assembly model is heated by the direct 

current passing through the fuel element simulators with uniform power density distribution along 

the FA height. Cable thermocouples of 1.5 mm OD are sealed in the fuel element simulator walls 

(Fig. 2.3). 

Eleven RBMK-1500 reactor spacing grids-intensifiers with the full number of cells with pitch of 

360 mm were installed in the upper part of the heated section along 3600 mm length. 20 grids

intensifiers of RBMK-1500 reactor were placed between them with 120 mm pitch, which served as 

spacers only for 6 fuel elements of the inner row. Nine authorized standard grids with 360 mm pitch 

were mounted in the lower part of the FA model. 

The RBMK-1500 channel design differs from that of RBMK-1000 by spacer grids, which are 

equipped with heat exchange intensifiers in the FA upper part. Availability of these intensifiers in 

the upper part of the FA allows increasing in channel heat power. 

The lower halves of RBMK-1500 and RBMK-1000 fuel assemblies are identical. Therefore some 

experimental results obtained in this experiment concerning the lower assembly half are applicable 

for RBMK-1000 (for instance, dryout onset, post dryout heat transfer...).

3
Fig. 2.1. KS RBMK MFCC model. 

4
Fig. 2.3. Cable th

Fig. 2.2. Fuel channel model cross section. 

ler PSR-72 Thermocouple of KTMS wire dia. 1 

Lel rod simulator 

ermocouple placement into the wall of the fuel rod simul 

5

lator.
There is also equipment that simulates operation of reactor drum separators (DS), steam condensers, 

downcomers and main circulation pumps of the RBMK primary circuit. However, this equipment 

do not model the appropriate RBMK MFCC components. For this reason the RBMK primary 

circuit model at the KS test facility is considered as semi-integral one. 

Processes in the parallel fuel channels are under consideration during this experiment. One of the 

channels is considered as a full-size model of RBMK fuel channel. Impact of the rest parallel 

channels is simulated with the FC bypass (18). A great flow rate through the FC bypass provides 

practically constant pressure drop between the upper and lower headers in the course of the 

experiment. 

The pressurization system used in the experiment includes 6 pressurizers of 0.52 m3 in total volume 

connected to the I-st collecting header. Nitrogen was used by way of gas medium. 

More detailed description of RBMK MFCC model at the KS test facility is in [2]. 

3. DESCRIPTION OF THE TEST 

The mode parameters in the course of the series of the tests were varied in the following ranges: 

* FA model power: 1691 - 4566 kW; 

* FA model inlet pressure: 7.68 - 8.74 MPa; 

* FC model inlet temperature: 516 - 533 K; 

* FC model inlet flow rate 3.9 - 6.27 kg/s. 

Before the beginning chosen Test 5, the initial steady state with coolant forced circulation was set at 

given initial parameters outlined in Table 3.1. 

Table 3.1. Parameters of the initial steady state for KS RBMK- 1500 Test 5. 

Designation of N G Pin Tin DP16-4 

experiment kW Kg/s MPa K MPa 

KS RBMK-1500 

Test 5 2486 4.70 8.40 527.4 0.2616

6
Given value of flow rate through the FC model was provided with an isolating control valve (see 4 

in Fig.2.1). At given head-flow rate characteristic of the pumps a required total water flow rate 

through the FC model and FC bypass is provided with valve situated on the pump bypass. 

Required flow rate distribution between MFCC and pump bypass is provided with matching local 

hydraulic resistance of the valve situated on the pump bypass at computer simulating of the test. 

The FC model conditions during the experiment are nearly close to those when breaking the MCP's 

pressure header in the RBMK reactor and cutting off fuel channels with check valves. 

When limiting temperature (this temperature mustn't be more than 870 K) is reached on the fuel rod 

simulator surface there is a resumption of flow rate through the fuel channel. Thus coolant 

circulation recovery on account of ECCS operation was simulated. The test is carried out at 

constant electrical power of the FA model. 

Coolant been supplied from the pumps (13) went up through the riser of the fuel channel model (6, 

7) and also through the FC bypass (17) up to the upper header (10) and then descended through four 

downcomers of RBMK MFCC model down to the suction side of the pumps. 

Upon achieving a steady state, parameter recording began and an isolating control valve (4) at the 

inlet to the FC model closed completely and rapidly (during 3 s) causing the decrease in coolant 

flow rate down to zero. At achieving predetermined limit temperature of the rod simulators, an 

isolating control valve quickly opened and coolant flow rate recovered. In this case, temperature of 

the fuel element simulators decreased down to that close to saturation one. 

States of the rest valve on the FC bypass and also the valves on the four downcomers and on the 

pump bypass were unchangeable during the transient. 

During transient, a flow rate through the FC bypass remained practically constant (about 33.3 kg/s 

within the limits of experimental error). In the course of the experiment pressure in the upper header 

and separation columns was not maintained constant. The measurements scheme is shown in 

Fig.3.1.

7
The following parameters, outlined in Table 3.2, were measured and registered in the course of the 

experiment. 

Table 3.2. List of measured parameters and measurement errors. 

Parameter Absolute measurement error 

FA model electrical power N ± 60 kW 

Water mass flow rate G at the FC inlet ± 0.14 kg/s 

Pressure Pin at the FA model lower part ± 0.15 MPa 

Pressure drop DP16-4 on the FA model ± 0.1 KPa 

height 

Water temperature Tin at the FA model inlet +6 K 

FE simulator wall temperatures Twl - Tw4 + 16.5 K 

along the height of the FA model 

The range of non-sensibility of the differential pressure gage is 0 - 120 KPa, because the device for 

measuring the pressure drop DP16-4 reached its lower measurement limit equal to 120 KPa. 

According to special tests, response time of the thermocouples was 0.3 s.

8
To separators

To heat exchangers 

P SWC model

Sampling 4

ILWC modE

circulation pum

Fig. 3.1. Measurements scheme.

9
4. DESCRIPTIONS OF RELAP5 MODELS AND BASE CASE INPUT DECKS FOR THE 

TEST 

4.1. RELAP5/MOD3.2 model and assumptions 

4.1.1. Main allowances for simulation of the test 

When calculating and assessing suitability of RELAP5/MOD3.2 and its modeling units for 

description of separate phenomena and complex processes, it is conventional in the first stage of the 

code simulation to use the options recommended by the code developers for actuating the code 

models under analogous conditions. The general modeling approaches recommended in the 

RELAP5 manuals [3, 4] should continue to be used. 

The following assumptions were made: 

" Volume Vertical Stratification, Water Packing, Abrupt Area Change, Branching, Noncondesables, Umbrella Model were process models activated for the corresponding circuit 

components; 

" Process models such as an additional model of countercurrent flow limitation (CCFL Model), model of critical mass flow rate (Choked Model), and Reflood Model were not to be used in the 

corresponding circuit components. 

To describe interphase friction in the coolant in the FC model with the FA, an option designating to 

rod bundle (with flag b=l) is applied. Semi-implicit scheme of numerical integration specified with 

the tt=3 option is used to calculate conjugate hydrodynamics and heat transfer/conduction 

processes. 

4.1.2. KS RBMK MFCC model nodalization and input data description 

RELAP5/MOD3.2 model simulates RBMK MFCC model at the KS test facility. This model 

includes a riser being investigated that contains two branches with models of the MFCC 

components, and auxiliary downcomer of four branches including components that ensure initial 

and boundary conditions in the MFCC part under consideration and also the test facility operation 

as a whole. Nodalization scheme for RBMK MFCC model at the KS test facility (in terms of 

RELAP5) is presented in Fig. 4.1. This nodalization scheme and input decks were developed with 

regard to the main assumptions when carrying out computer analysis of the test.

10
Fig. 4.1. Nodalization scheme of the RBMK MFCC model at the KS test facility. 

To simulate operation of each pump when them activated simultaneously it was necessary to use 

conjectural homological head and torque curves for 8 single-phase modes of TsEN-146 pumps. 

During the experiments the pumps operated continuously in single-phase flow at the wheel velocity 

of 3000 rpm. 

At given head/flow characteristics of TsEN-146 pumps for normal operating conditions, required 

total water flow rate through the FC model and channel bypass is provided with the valve in the 

pumps bypass. This valve is modeled with component mtrvlv79. Given distribution of flow rates 

between MFCC model and pumps bypass is provided with choosing local hydraulic resistance of 

the valve component (mtrvlv79) during computer modeling of the experiment. Positions of the 

valve on the FC bypass (in Fig. 4.1 an orifice of constant local hydraulic resistance 4=135 is shown 

instead of the FC bypass valve) and the valve on the pumps bypass were not changed during the 

transient under investigation. 

Taking into account a great quantity of components in the primary and secondary circuits of the KS

I1
test facility, it was used only one equivalent component when modeling each appropriate group of 

the typical components located in four branches of the downcomer. In particular, only one 

component vol. 20 is used to simulate three separators (11). Three condensers (14) are modeled 

with one component vol. 32. When developing these equivalent models, particular attention was 

given to parity between real volumes and lengths of the inlet and outlet pipelines and those of 

corresponding hydrodynamic components as well as between surface areas of heat transfer toward 

water in the second circuit. These conditions are necessary to bring about representation of 

experimental conditions of heat exchange between primary and secondary circuits and to ensure 

simulation of coolant pressure behavior in the primary circuit at transient under investigation. To do 

this the modeling of circuit volume sections with two-phase mixture and gas must be obviously 

suitable. 

Coolant flow termination to the FC model inlet with successive flow resumption are simulated with 

closing and next opening of ICV that uses a component like "motor valve 2". To control valve 

"close" and "open" procedures at given time moments Trip Input Data are used. 

When modeling the section of the fuel channel with the FA model it was chosen a fine nodalization 

for hydrodynamic components and heat structures along the channel height that was connected to 

the pitches between spacer grids and grid-intensifiers (see Fig. 4.2). 

The alignment of the nodalization in the fuel channel with the grid spacers is presented in Table 4.1. 

However, this resulting grid does not align well with some of the temperature and pressure 

measuring positions. This adds an uncertainty (< 1%) when comparing calculated and experimental 

values. 

Table 4.1. The alignment of the nodalization in the fuel channel with the grid spacers. 

Experimental Closest Component in RELAP Model 

Measurement Height Component Input Node Center Node Span 

[m] Deck Height Height 

1[n] [in] 

DP16-4 bottom 0.186 vol. 5, node 3 0.340 0.160 - 0.520 

PIN 1.586 vol. 5, node 6 1.420 1.240- 1.600 

DP16-4 top 6.836 vol. 5, node 40 6.820 6.760 - 6.880 

TW4 1.044 ht. st. 51, node 4 1.060 0.880 - 1.240 

TW3 3.814 ht. st. 51, node 14 3.820 3.760 - 3.880 

TW2 6.854 ht. st. 51, node 39 6.820 6.760 - 6.880 

TWi 6.894 ht. st. 51, node 40 6.940 6.880 - 7.000

12
Fig. 4.2. Nodalization scheme of the RBMK-1500 Fuel channel model. 

13
Rod simulator walls were modeled with "heat structure" components with internal heat sources. 

Boundary conditions on the rod's outer surfaces were set with Right Boundary Condition Cards 

with boundary condition type W3 (I)=110 ("Vertical bundle without cross flow" with P/D = 

16.5/13.5= 1.222 on 901-940 cards). Heat transfer hydraulic diameter (i.e., heated equivalent 

diameter) De=l 1.92 mm is used for fuel channel with the 19-rods bundle (with 18 heated rods). 

To account the heat exchange processes to be impact by the grids, it were used "Additional Right 

Boundary Cards". Local hydraulic resistance t--0.55 are to simulate 9 spacer grids arranged with 

the pitch of 360 mm in the lower part of the heated region. For 11 grid intensifiers situated with the 

pitch of 360 mm in the upper part of the heated region, local hydraulic resistance are defined to be 

t=0.91. As for 20 grid intensifiers, which are in the upper part of the heated region having the pitch 

of 120 mm, their local hydraulic resistance are equal to t=0.28. 

In the "base case" calculations, power density distribution in the fuel rod simulators over the FA 

cross section was non-uniform. Power of 12 rods in the peripheral row was higher than rod power 

in the inner row of the bundle, because of the real radial power peaking factor of the FA model was 

1.061. 

The rod simulator wall is portioned in thickness into 4 layers so that the external layer thickness is 

0.75 mm corresponding to the deepness at which the thermocouple's hot junction is positioned in 

the wall. This enables a direct comparison of RELAP5/MOD3.2 calculation results for wall 

temperature at this depth with the test data on temperatures Twl, Tw2, Tw3 and Tw4. 

Channel walls of the riser and descending circuit sections to the points of the condenser, heat 

exchanger and aftercooler were also modeled with "heat structure" components in order to simulate 

heat accumulation in the metal and external heat losses. 

External heat losses from the primary circuit are modeled with setting up the heat transfer 

coefficient to be K=10 W/[m2 K]. This value is constant in the region from the external surface of 

the heat structure which models the channel wall to the points of time-independent temperature of 

295 K.

14
4.1.3. Methods of computer modeling of the experiment 

This computer model makes it possible to simulate directly the experiment. When computer 

modeling the experiment the problem is setting up adequate thermal hydraulic characteristics of the 

components in the primary and secondary circuits (in the auxiliary section). 

Using valve mtrvlv2, it is especially difficult to ensure experimental time-dependency of the 

coolant flow rate at the FC inlet obtained in the test. Because of it there was special computer 

simulation method and an Input Deck developed for the test. 

When modeling the initial steady state with forced circulation, a balance between the FA power and 

heat removal in the condenser, heat exchanger and aftercooler was achieved with setting 

distribution of primary circuit coolant flows between descending branches and choosing water 

temperature in the secondary circuit. In this case, circuit pressure Pin, coolant temperature Tin and 

flow rate G through the FA model were stabilized after reaching the values equal to corresponding 

initial parameters obtained in the test at the moment texp=O within the measurement error. Mass 

inventory in the primary circuit of MFCC was also stabilized. Water flow rate about 33.3 kg/s 

within the limits of experimental error through the bypass was set at a constant local hydraulic 

resistance t=135 of the valve on the FC bypass. Given flow rate at the FC inlet was ensured with 

the valve mtrvlv2, which local hydraulic resistance 4=770 was chosen in the course of computer 

modeling for the test. 

Calculations of this preset regime were run during tcalc=1000 seconds for stabilizing coolant 

parameters and heat structure temperatures in the primary circuit. Before this took place, the volume 

TDV100 containing subcooling water was connected to the primary circuit model. The water 

temperature equal to required value Tin at the FC inlet and also the pressure for supporting required 

pressure Pin in the channel at the moment texp=0 were set in this volume. 

Vary small or close to zero values of water flow rates in the conjunctions SJ93 and SJ101 and, 

consequently, stabilization of mass inventory in the primary circuit were also demonstrations of 

stabilization of the processes in the primary and secondary circuits. 

After achieving the steady state in the primary circuit at required coolant mode parameters at the FC 

inlet, the volume TDV100 was disconnected from the primary circuit of MFCC model and a closed 

primary circulation circuit including the pressurizer was formed. In so doing, only the pressurizer 

with subcooled water was connected to the primary circuit model. In the pressurizer, liquid level 

was preset to be in the middle of its vessel, as for liquid temperature its value was equal to Tin i.e.

15
the initial magnitude required at the FC inlet. Gas (nitrogen) pressure was specified to ensure a 

given FC pressure Pin at the moment texp=O s. Stabilization of the calculated pressures P(t)calc and 

volume equilibrium qualities Xe(t)calc at the inlet and outlet of the FA model were also 

demonstrations of stabilization of the processes in the primary and secondary circuits during the 

time interval from tcalc=1000 s to tcalc=1400 s. 

Simulation of the curve of sharp decrease in water flow rate down to zero at the FC model inlet with 

valve mtrvlv2 was performed by choosing its close rate and a related value of its initial position as 

well as moments to begin its opening and closing. The FA power was unchanged during the test. 

When the rod simulator temperature preset limit was reached (it should not be above 870 K) valve 

2r was quickly opened with coolant flow being recovered. In this case, the rod simulator 

temperatures were decreased down those closed to saturation temperature. Simulation of the curve 

of sharp increase in water flow rate at the FC model inlet up to a given value with valve mtrvlv2 

was performed by choosing its opening rate as well as moments to begin its opening and closing. 

This flow rate was smaller than the initial one at the moment texp= 0 s. 

When modeling transient in the fuel channel with the FA model, it was chosen a maximum time 

step dtmax =0.01 s. This value is in agreement with the recommendations [3, 4] for calculating such 

processes. 

4.2. RELAP5IMOD3.2.2 GAMMA model and assumptions 

When calculating and assessing suitability of RELAP5/MOD3.2.2 GAMMA and its modeling units 

for description of separate phenomena and complex processes, it is conventional to use the options 

recommended by the code developers for actuating the code models under analogous conditions. 

The following assumptions were made: 

"* Volume Vertical Stratification, Water Packing, Abrupt Area Change, Branching, Noncondesables, Umbrella Model and Reflood Model were process models activated for the 

corresponding circuit components; 

"* Process models such as an additional model of countercurrent flow limitation (CCFL Model), model of critical mass flow rate (Choked Model) were not to be used in the corresponding 

circuit components. 

When modeling transient in the fuel channel with the FA model, it was chosen a maximum time 

step dtmax =0.01 s.

16
5. RESULTS OF THE CODES ASSESSMENT

5.1. RELAP5/MOD3.2 base case results, comparisons to KS test data and conclusions 

Calculation of presetting mode with TDV100 been connected was performed during first 1000 s 

and then, after disconnecting TDV100, was continued up to 1400 s for achieving a steady state in 

the primary circuit. When calculating both preset mode and transient under investigation, option 

TRANSNT was used. To justify the basic nodalization scheme, methods for modeling of the test 

and corresponding input deck, preliminary calculations of the experiment were performed. 

Calculation results and test data for the main mode parameters Gin, Tin, and Pin at the FC inlet 

under steady conditions with forced circulation are presented in Figures 1, 2 and 3, respectively, in 

Appendix B and in Table 5.1 to be compared. In these figures and in the table, one can see the 

calculated values of mentioned parameters at the steady state are close to the experimental ones or 

they lie within the range of measurement accuracy. During the test the steady state is considered a 

mode to be in the interval of time from texp=O s to the moment when water flow rate begins to 

decrease. 

To estimate suitability of computer modeling of complex thermal hydraulic processes in the FC 

with FA model at the steady state the base case calculation results of the total pressure drop DP16-4 

and rod's wall temperatures Twl, Tw2, Tw3, Tw4 across the FA model height were used. These 

base case results are presented in Figures 4 - 8 in Appendix B and in Table 5.1 to be compared with 

test data, too. 

As an integral criterion for the suitability assessment of simulation of thermal hydraulic processes 

in the channel with the RBMK-1500 fuel assembly, it was used the value of relative mismatching of 

total pressure drop DP16-4 along the FA model height which is determined as follows: 

DPcdc- DP a(p DP ep 

For comparison, Table 5.1 lists calculation results and data for DP16-4 obtained during the test. 

In the preliminary case with FC wall roughness 4.10-6 m the code gives - 9.7 % underestimation in 

pressure drop DP16-4 relating to the measured value in the steady state. This discrepancy for total 

pressure drop DP16-4 may be resulted from inaccurate code description of the local losses of 

pressure on the spacer grids and grid-intensifiers as well as wall and interphase frictions in the two17
phase flow in the heated rod bundle. There needs to be some effort to address this error via 

parametric changes in the input. Therefore, sensitivity study was performed with different FC wall 

roughness for the test. 

In the base case calculation with FC wall roughness 4-10-5 m the code gives + 5.4 % overestimation 

in pressure drop DP16-4 relating to the measured value in the steady state. The increasing of the FC 

wall roughness in 10 times results in code over prediction for DP16-4 pressure drop, however the 

base case calculated value of pressure drop DPI 6-4 is in a satisfactory agreement with the measured 

one. 

The calculated values of the rod temperatures Twl, Tw2, Tw3, Tw4 along the FA height are in 

satisfactory agreements with the test data, too. In steady state the code describes with a reasonable 

suitability a heat transfer in two-phase flow in the channel with the RBMK-1500 fuel assembly. 

Table 5.1. Comparison of the base case calculated, sensitivity studied and experimental values of 

the main mode parameters at the steady state. 

Steady state N Gin Pin Tin C-bypss Total pressure Mismatching 

parameters kW Kg/s MPa K Kg/s drop DP16-4, Pa ± A (DP16-4), % 

5 (experiment) 2486 4.70 8.40 527.4 33.3 261600 

5 (calculation 

with roughness 

4-10-6 m) 2486 4.73 8.38 526.5 30.8 236290 - 9.7 

5 (base case 

calculation with 

roughness 4.10-5 2486 4.62 8.42 526.5 30.8 275820 + 5.4 

m)

18
RELAP51MOD3.2 describes with a reasonable suitability the complex processes at the stage of 

the transient in the test when the coolant flow rate decreases and completely terminates. 

In particular, the pictures of the experimental and calculated pressures P (t) are in a qualitative 

agreement, although at certain stages the calculated one is higher or lower than measured value in 

the transient. At the same time, the rates of the increase or decrease in pressures dP/dt as well as 

finally achieved pressure values are essentially different from those obtained experimentally (see 

Fig. B-3). Predicted pattern of the behavior of total pressure drop DP16-4 (t) is in a qualitative 

agreement with experimental data. The reasons for these discrepancies when describing the 1-st 

stage of the transient may be a non-adequate code description of dynamic processes of steam 

generation in the FC with FA as well as steam condensation in the components of the closed circuit 

as a whole and, consequently, non-adequate description of the pressure behavior in the primary 

circuit and in the fuel channel. 

RELAP5/MOD3.2 code reasonably describes the character and rate of the thermal and 

hydrodynamic processes and the behaviors of the parameters concerned in the first stage of the 

transient. To assess integrally an accuracy of the code simulation of the complex processes, the time 

interval At, (from the moment of full stop of flow to the beginning of increase in wall temperature 

Tw I (t) at the FA outlet) was used. The value of the time interval Atd=td - t (GO) been predicted for 

the test exceeds the experimental value At, by about -1.0 s. This indicates a reasonable suitability of 

the code simulation of the dryout initiation and its propagation along the FA height during the 1-st 

stage of the transient. The results would be still closer to the test data when simulating the flow rate 

behavior at the FC inlet as in a reality. Use of Time Dependent Junction to accurate code simulation 

of a real flow rate behavior at the channel inlet gives more realistic code results for the initial and 

boundary conditions for the fuel channel during the test. 

The comparisons of the behaviors of rod's wall temperatures Twl (t), Tw2 (t), Tw3 (t), and Tw4 (t) 

been measured and also those of calculated wall temperatures during the transient in the experiment 

are presented in Figures B-5, B-6, B-7 and B-8, respectively. 

When simulating the test, the dryout primarily happens at the FA outlet leading to an increase in 

temperatures TwI (t) and Tw2 (t), as evident from Fig. B-5, B-6. Then the dryout propagates with 

time from top to bottom along the FA height. This predicted picture of the dryout initiation and its 

propagation from the top down along the FA height is in a qualitative agreement with test data. 

This indicates a reasonable suitability of the code simulation of the dryout initiation and its 

propagation along the FA height during the 1-st stage of the transient at FA power been constant.

19
It should be specially noticed that the maximum values Tw (t)mcalc of the calculated wall 

temperatures exceed the maximum experimental magnitudes Tw(t)a exp. It means that the code 

would be likely to overestimate the maximum cladding temperature, which would be a conservative 

result from a safety perspective. 

The reflood model does not behave in RELAP5/MOD3.2, therefore the second stage of the 

investigated transient in the test was simulated under conditions when a special reflood model is not 

in usage. This allowed to make more exact the conditions for modeling the thermal and 

hydrodynamic processes as well as to estimate a necessity and importance of a special code model 

to be used for analyzing of reflood during the second stage of the transient. 

The adequate code simulation of the complex processes at the first stage of the transient allow 

exactly modeling the initial conditions for the second stage of the transient 

The code gives an insufficient agreement with test data concerning the time characteristics and 

conditions of the rod surface quenching in the upper pait of the FA model. The code gives only a 

qualitative agreement demonstrating a presence of rod surface quenching in the lower FA part in the 

cross-section where thermocouple Tw4 is installed (see Fig. B-8). At the same time, the rest of the 

cross-sections been positioned above (see thermocouples Tw1 (t), Tw2 (t), Tw3 (t) in Figures B-5, 

B-6, B-7) do not quench during the 2-nd stage when calculating the experiment during 40 seconds. 

Shown is that the calculated velocity of quench front propagation is less than that in the test at 

constant power N=2486 kW. 

The analysis results obtained when modeling the reflooding of FC with RBMK-1500 fuel assembly 

allow RELAP5/MOD3.2 code suitability being assessed as insufficient. Shown is a necessity and 

importance of a special Reflood Model to be used for suitable description of the second stage of the 

transient. At validation of the advanced code version RELAP5IMOD3.2.2 GAMMA and 

assessment of its reflood model, it will be necessary to achieve a suitable simulation of the initial 

conditions for the second stage of the transient.

20
The results of RELAP5/MOD3.2 code assessment are presented in Table 5.2.

Table 5.2. The results of RELAP5/MOD3.2 code assessment (code performance for 

process/phenomenon). 

1. Process/Phenomenon in the steady state in Test 5 Results of RELAP5/MOD3.2 

assessment 

1.1. Total pressure drop along the height of the channel with Reasonable adequacy 

RBMK-1500 fuel assembly 

1.2. Heat transfer in the two-phase flow in the channel with the Reasonable adequacy 

RBMK-1500 fuel assembly 

2. Process/Phenomenon on the stage of decrease and full stop of Results of RELAP5/MOD3.2 

flow in Test 5 assessment 

2.1. Total pressure drop and water release from the fuel channel Reasonable adequacy 

model and heated rod surface dryout 

2.2. Dryout under sharp flow deceleration at the inlet of the Reasonable adequacy 

RBMK-1500 fuel assembly 

2.4. Post dryout heat transfer and heated rod bundle temperature Reasonable adequacy 

behavior in the lower and upper parts of RBMK- 1500 fuel 

assembly under stop of flow and channel drying conditions 

3. Process/Phenomenon on the recovery stage of water supply Results of RELAPS/MOD3.2 

into the fuel channel model assessment 

3.1. Propagation of the reflood and quench fronts in the RBMK- Insufficient adequacy 

1500 fuel assembly under flow resumption at the channel inlet

21
5.2. RELAP5/MOD3.2.2 GAMMA base case results, comparisons to KS test data and 

conclusions 

Calculation of presetting mode with TDV100 been connected was performed during first 1000 s 

and then, after disconnecting TDV100, was continued up to 1400 s for achieving a steady state in 

the primary circuit. 

RELAP5IMOD3.2.2 GAMMA results and test data for the main mode parameters Gin and Pin at 

the FC inlet under steady conditions with forced circulation are presented in Figures C-I and C-2, 

respectively, in Appendix C to be compared. In these figures one can see the calculated values of 

mentioned parameters at the steady state are close to the experimental ones. 

The base case results for total pressure drop DP16-4 and rod's wall temperatures Twl, Tw2, Tw3, 

Tw4 across the FA model height are presented in Figures C-2, C-3, C-4 in Appendix C to be 

compared with test data. The code gives + 5.4 % overestimation in pressure drop DP16-4 relating to 

the measured value in the steady state. The calculated values of the rod's wall temperatures along 

the FA height are in satisfactory agreements with test data, too. In steady state the code describes 

with a reasonable suitability a heat transfer in two-phase flow in the channel with the RBMK-1500 

fuel assembly. 

RELAP5/MOD3.2.2 GAMMA describes with a reasonable suitability the complex processes at 

the first stage of the transient with stop of flow. 

The pictures of the experimental and calculated pressures P (t) are in a qualitative agreement, 

although at certain stages the calculated pressure is higher or lower than measured one in the 

transient (see Fig. C-2). Predicted pattern of the behavior of total pressure drop DP16-4 (t) is in a 

qualitative agreement with test data. The reasons for these discrepancies when describing the 1-st 

stage of the transient may be a non-adequate code description of dynamic processes of steam 

generation in the fuel channel as well as steam condensation in the components of the closed circuit 

as a whole and, consequently, non-adequate description of pressure behavior in the primary circuit 

and in the fuel channel. 

RELAP5/MOD3.2.2 GAMMA code reasonably describes the character and rate of the thermal and 

hydrodynamic processes and the behaviors of the parameters concerned in the 1-st stage of the 

transient Comparisons between test data and RELAP5/MOD3.2 and RELAP5/MOD3.2.2 

GAMMA predictions for the behaviors of the considered parameters in the base case with "motor 

valve 2r" are presented in Appendix C. The comparisons of the behaviors of rod's wall 

temperatures Twl (t), Tw2 (t), Tw3 (t), and Tw4 (t) been measured and also those of calculated

22
temperatures during the transient are presented in Figures C-3, C-4 and C-5. These indicate a 

reasonable suitability of the code simulation of the dryout initiation and its propagation along the 

FA height during the 1-st stage of the transient at FA power been constant. The maximum values 

Tw (t),axcalc of the calculated wall temperatures exceed the maximum experimental magnitudes 

Tw(t)r exp. It means that RELAP5/MOD3.2.2 GAMMA code would be likely to overestimate the 

maximum cladding temperature, which would be a conservative result from a safety perspective. 

The reflood model behaves in RELAP5/MOD3.2.2 GAMMA code, therefore the transient in the 

test was simulated using a special reflood model. This allowed to assess adequacy of a special 

model for analyzing of reflood during the second stage of the transient. 

The adequate code simulation of the complex processes at the first stage of the transient allow 

exactly modeling the initial conditions for the second stage of the transient with FC reflood. 

The code gives reasonable agreements with test data concerning the time characteristics and 

conditions of the rod surface quenching in the upper part of the FA model (see thermocouples TwI 

(t) and Tw2 (t) at the elevations 6.94 m and 6.82 m, respectively, in Figure C-3). The code gives 

only a qualitative agreement demonstrating a presence of rod surface quenching in the middle FA 

part (see thermocouple Tw3 (t) at the elevation 3.82 m in Figure C-4). 

At the same time, the cross-section been positioned below does not quench during the 2-nd stage 

when calculating the experiment during 40 or 350 seconds (see temperatures Tw (tcalc) at the 

elevation 1.04 m in Figures C-4 and C-5). Shown is an insufficient code adequacy for the lower FA 

model part 

RELAP5/MOD3.2.2 GAMMA results obtained when simulating reflood and quench fronts in the 

fuel cannel model allow the code adequacy being assessed as a reasonable adequacy for the upper 

part of RBMK-1500 fuel assembly model and an insufficient adequacy for its lower part. 

Shown is a necessity for formulation special Standard Problem "Propagation of the reflood and 

quench fronts in the lower and upper parts of RBMK-1500 fuel assembly model under flow 

resumption at the channel inlet" and its analysis using RELAP5/MOD3.2.2 GAMMA

23
The results of RELAP5/MOD3.2.2 GAMMA code assessment are presented in Table 5.3. 

Table 5.3. The results of RELAP5/MOD3.2.2 GAMMA code assessment (code performance for 

process/phenomenon) 

1. Process/Phenomenon in the steady state in Test 5 Results of 

RELAP5/MOD3.2.2 

GAMMA assessment 

1.1. Total pressure drop along the height of the channel with RBMK- Reasonable adequacy 

1500 fuel assembly model 

1.2. Heat transfer in the two-phase flow in the channel with the Reasonable adequacy 

RBMK-1500 fuel assembly model 

2. Process/Phenomenon on the stage of decrease and full stop offlow Results of 

in Test 5 RELAP5/MOD3.2.2 

GAMMA assessment 

2.1. Total pressure drop and water release from the fuel channel Reasonable adequacy 

model and heated rod surface dryout 

2.2. Dryout under sharp flow deceleration at the inlet of the RBMK- Reasonable adequacy 

1500 fuel assembly model 

2.4. Post dryout heat transfer and heated rod bundle temperature Reasonable adequacy 

behavior in the lower and upper parts of RBMK-1500 fuel assembly 

model under stop of flow and channel drying conditions 

3. Process/Phenomenon on the recovery stage of water supply into Results of 

the fuel channel model RELAP5/MOD3.2.2 

GAMMA assessment 

3.1. Propagation of the reflood and quench fronts in the lower and Reasonable adequacy for 

upper parts of RBMK-1500 fuel assembly model under flow the upper FA model part resumption at the channel inlet Insufficient adequacy for 

the lower FA model part

24
6. SENSITIVITY STUDY

Sensitivity studies were performed with different FC wall roughness 4-10- m and 4-10-5 m in the FC 

model to estimate its influence on code simulation of complex thermal hydraulic processes in the 

FC. In steady conditions the increasing in FC wall roughness leads to a better agreement between 

experimental and calculated values of pressure drop DP16-4 across the FA model height with 

achieving good coincidence within the measurement accuracy for test 5 at FA power of 2486 kW. 

The increased FC wall roughness weakly influences on the behavior of pressure drop DP16-4 (t), 

and also of the wall temperatures Twl (t), Tw2 (t), Tw3 (t), and Tw4 (t)) during the 1-st and 2-nd 

stages of the transient. 

Also, sensitivity study was carried out to investigate the effects of modeling on the behaviors of the 

rod simulator temperatures along the heated bundle height using motor valve component or Time 

Dependent Junction in LWC. 

Comparisons between test data and RELAP5/MOD3.2.2 GAMMA predictions for the behaviors of 

the considered parameters G (t), Pin (t) and DP16-4 (t) in the base case with "motor valve 2r" and in 

the sensitivity study case with TDJ in LWC are presented in Figures D-1 and D-2 in Appendix D. 

The comparisons of the behaviors of rod's wall temperatures TwI (t), Tw2 (t), Tw3 (t), and Tw4 (t) 

been measured and also those of calculated temperatures during the transient are presented in 

Figures D-3 and D-4. These indicate a reasonable suitability of the code simulation of the dryout 

initiation and its propagation along the FA height during the 1-st stage of the transient at FA power 

been constant. 

Using two lumped rod simulators (Kr=l.061) and TDJ to accurate code simulation of the real flow 

rate behavior at the channel inlet gives more realistic code results for the initial and boundary 

conditions in the fuel channel. In this case the code predicted time interval Atd from the moment 

t(GO) of complete stop flow to the beginning td of the rod's wall temperature Twl (t) increase at the 

core outlet exceeds the experimental value Atd by about - 0.2 s. The excess of calculated value Atd 

over that obtained experimentally decreases from - 1.0 s to - 0.2 s and the pictures of the dryout 

initiation and its propagation along the FA height become more resembling in this case.

25
7. RUN STATISTICS 

The simulation model for KS Test 5 includes: 

307 volumes, 311 junctions, 282 heat structures with 729 nodes. 

There were the following resources been used for the calculation: 

Run time - CPU = 855.13 s; 

Step number - DT = 3751; 

Volume number - C = 307. 

Calculation results of grind time (program efficiency factor) 

Grind time= _ = 0.74259 

C.DT 

For the calculations, it was used a computer IBM PC AT with processor INTEL Pentium

166MMX. Windows-95 was used as an operating system. CPU-time as well as the integration step 

variations are presented in Fig. 7.1 and 7.2, respectively.

8400,_ 

.8200 ____ 

8000_____ ___ _ 

780013 

7400• ....

0

C-,

Time (s) 

Fig. 7. 1. Execution time (CPU TIME) of the main variant computation for the experiment.

26
0.0200 

0.0175 

0.0150 

0.0125 

•0.0100 

0.0075 

0.0050 

0.0025

ie ieee ~ - ~ 

0.0001 15 20 2 0 3

0...... 0 .. . .. . .. . . .• 15... .. . . 2o1 .. .. 25 " s o 35 Tire (s) 

Fig. 7.2. Integration step (dt) variations at the main variant computation for the experiment. 

8. SUMMARY OF CONCLUSIONS 

KS test data on the behavior of the heated rod bundle temperature in the RBMK-1500 core model 

under stop and recovery flow conditions were simulated with RELAP5/MOD3.2 and 

RELAP5/MOD3.2.2GAMMA to assess these codes suitability. Especially calculations were 

performed to estimate differences in the code version predictions for processes/phenomena, which 

could occur under specific conditions of RBMK type reactor during LOCA with MCP's pressure 

header rupture and subsequent ECCS water injection. This problem addresses phenomena of high 

importance to RBMK-1500 safety including water discharge, critical heat flux, post dryout heat 

transfer, reflood and propagation of rewetting front in the fuel channel during an accident. 

In this work some deficiencies of RELAP5/MOD3.2 and RELAP5/MOD3.2.2GAMMA in analyses 

of KS Test 5 could be identified, and the following conclusions can be drawn: 

* RELAP5/MOD3.2 gives reasonable agreements of general pictures of simulated 

processes/phenomena with test data on the stage with the decrease and complete stop of flow at the 

FC inlet. At the same time, it was intimated that there is a need to modify RELAP5/MOD3.2 

models used for interphase friction and critical heat flux in the channel with the RBMK-1500 fuel 

assembly under initial steady conditions with forced circulation. 

* When simulating the recovery stage of water supply into the channel there were essential 

distinctions between RELAP5JMOD3.2 code results and test data on the behaviors of the rod's wall 

temperatures along the FA height. The code does not give qualitative agreements between the 

curves for the rod temperatures along the FA height at the quenching in the test. The code gives 

insufficient agreement with test data concerning the time characteristics and conditions of the rod

27

______ I. L I. 4 4
surface quenching in the upper and middle parts of the FA. The analysis results allow 

RELAP5/MOD3.2 code suitability being assessed as insufficient. Shown is a necessity and 

importance of a special reflood model to be used for suitable description of the reflood stage of the 

transient. 

9 RELAP5/MOD3.2.2 GAMMA gives reasonable agreements of general pictures of simulated 

processes/phenomena with test data on the transient stage with the decrease and complete stop of 

flow. Sensitivity study was carried out to investigate the effects of modeling on the behaviors of the 

rod simulator temperatures along the heated bundle height using motor valve component or Time 

Dependent Junction in LWC. Use of TDJ to accurate code simulation of the real flow rate behavior 

at the channel inlet gives more realistic code results for the initial and boundary conditions in the 

fuel channel. In this case the code predicted time interval Atd from the moment t(GO) of complete 

stop flow to the beginning td of the rod's wall temperature Twl(t) increase at the core outlet exceeds 

the experimental value Atd by about - 0.2 s. This indicates a reasonable adequacy of the code 

simulation of dryout initiation at rapid decrease of the flow right down to its total termination. 

* RELAP5/MOD3.2.2 GAMMA results obtained when simulating reflood and quench fronts in the 

fuel cannel allow the code adequacy being assessed as reasonable only for the upper part of RBMK

1500 fuel assembly and as insufficient for the lower part of the FA model. 

Shown is a necessity for formulation special Standard Problem "Propagation of the reflood and 

quench fronts in the lower and upper parts of RBMK-1500 fuel assembly under flow resumption at 

the channel inlet" and its analysis using RELAP5/MOD3.2.2 GAMMA. 

REFERENCES 

1 V.S.Osmachkin, V.A.Kapustin, L.L.Kobzar and others (RRC KI), O.Yu.Novoselsky (ENTEK). Results of investigation with KS test facility of temperature conditions of fuel 

channel model of NPP with RBMK-1500 accidents. RRC KI - ENTEK report, Reg.#32/345. 

1977. 30p (58). 

2. Computer code validation for transient analysis of VVER and RBMK reactors: Standard 

Problem INSCSP-R2 Definition "RBMK type reactor core thermal hydraulic processes investigation under pressure header break conditions", Experiments with KS RRC KI test 

facility, International Nuclear Center of Russia Minatom, Moscow, Russia (August 1999). 3. RELAP5/MOD3 Code Manual, Volume 4: Models and Correlations, INEL-95/0174, 

NUREG/CR-5535, 1995. 

4. RELAP5/MOD3 Code Manual, Volume 2: User's Guide and Input Requirements, INEL

95/0174, NUREG/CR-5535, 1995.

28
APPENDIX-A 

Original Data Plots From KS RBMK-1500 Test 5

A-1
-KKS RRgMK-1500l Tst 5 owerV Z-+00 KV~t 

J

I.) ./u 

Time (s)

Fig. A-1. Mass flow rate G history at the FC model inlet in experiment 5.

KS RBMK-1500 Test 5

350000 

300000- 

250000 

200000 

50000 

00000

50000_

U ...... 1 ... ...--. .. 1, -. i.i. I i

15 20 

Time (s)

25 30 40

Fig.A-2. Pressure drop P16-4 history along the FA model in experiment 5. 

A-2

8.0

•76.0 

04.0 

C/) 

Cf) 

2.0 

0.0

z2 3U 40

0. 

{D 

V_ 

-. ) 

I..

0

__ KS RBMK-I_•DN T•t =, •'A D ....... rlAO• I.LIr±

0 ll./ 35

35
9500000- KS RBMK-1500 Test 5 

9000000 

48500000 

8000000 

V)) 

V) 

0.7500000 

7000000 

6500000 ........

0 5 10

FA Power = 2486 kWt

2T Time (s)

Fig. A-3. Pressure Pin history in the lower part of the FA model in experiment 5. 

KS RBMK-1500 Test 5 FA Power = 2486 kWt 

900

S700 0) 

a

E 

I600

5002......... .... ý 0 5 10 15 20 25 30 35 40 

Time (s) 

Fig. A-4. Fuel rod simulator temperature Twl (z=6.894 m) history in experiment 5.

A-3

15 25 30 35 40
1000*i KS RBMK-1500 Test 5 FA Power = 2486 kWt

Q) 

0

E 

0) 

Iduo. 

800

700 

600,

__0 5 10 15 20 25 30 35 40 

Time (s) 

Fig. A-5. Fuel rod simulator temperature Tw2 (z=6.854 m) history in experiment 5. 

, KS RBMK-1500 Test 5 FA Power = 2486 kWt

r,) 

0) 

Q) 

E 

Q) 

I--

TI rV r

800- / 

700 

600 

500.___

0 5 10 15 0 2 0 5 40 

Time (s) 

Fig. A-6. Fuel rod simulator temperature Tw3 (z=3.814 m) history in experiment 5.

A-4

100.KS RBM IK-1500 ITest 5 FA Power = 2486 kWt
1000- . . . .. 

900

800

700-

600 ---------4 

600

500- -r1- 1-r- ..........- ,- ........ rr- -- y1T1-t -rrr7 r----rl rrT r,

0

Time (s)

Fig. A-7. Fuel rod simulator temperature Tw4 (z=1.044 m) history in experiment 5.

900

800. 

700

600-

KS RBMK-1500 Test. 5

0 5 10 15 20 

Time (s)

FA Power = 2486 kWt

Fig. A-8. Behavior of measured wall temperatures TwI, Tw2, Tw3 and Tw4 in experiment 5.

A-5

I

0 

0) 

0

E• 

'I.

40

1000

(36E)- Twl aaaa - Tw2 - -A-A- T-,"4 04-"$$-- Tw4

0_) 

41) 

E 

I--

500

K• RFIMK--15Ot3 Test 5 FA Power = 2486 kWt

5 ZD O30 O.D

25 30 35 40
Appendix B 

Comparisons between Test Data and RELAP5IMOD3.2 Base Case Results

B-I
(exp.5 BE E6- (caic) 

0 5 10 15 20 25 30 35 4C

Time (s) --

Fig. B-1. Mass flow rate G (t) history at the FC model inlet.

KS RBMK-1500 RFI APS/MOi.3 9

531 

•529

527 j3-&e- Ee4 43Aa -E~a-SB ....... SE33E B 3=6S3!eE33E 

525

523.

10 15 20 

Time (s)

25 35 40

Fig. B-2. Coolant temperature Tiri (t) history at the FC model inlet. 

B-2

8.0 

-•6.0 

04.0 

U) 

V) 

2.0 

0.0

0 

E 

Q)

521

0

S- Ti (exp.)I B - Ti (colc)

KS RBMK-1500

vv vw 0

5 30
Fig. B-3. Pressure P (t) history in the lower part of the FA model.

Fig. B-4. Pressure drop DP16-4 (t) history along the FA model.

B-3
KS RBMK-1500 1000 *1 ~ ~ ~ ~ ~ ____ ~ '-.,-)., C AD, /k-'' t..~

ý:uv____ ___ _ 

800:___ ____ ____ ___ 

700__ _ 

600 __ 

S- T•/1 (exp.) 

50)- • - htmp 0 A1520400)5

20 Time (s) 30 35

Fig. B-5. Fuel rod simulator temperature TwI (t) history.

... KS RBMK-1500 1000 ........ .... rE \ t.1r-MOU U3.2 

900 

800

700-_ ___• 

600 ; _n__ S-- -- - Twb2 (exp , 

500- ,1B f - hitemp 0 5203905 50 01rr -m ....... , r ......... I ......... .. .. . ........-. " ....... "2. .

Time (s)

"3U 40

Fig. B-6. Fuel rod simulator temperature Tw2 (t) history. 

B-4

Q) 

0

E 

Q) 

IQ) 

0

E 

Q)

25

i\ t.t..¢•l IVl V •JL,•. f_

0 5 25

v b35
Q) 

0. 

E 

QTime (s)

Fig. B-8. Fuel rod simulator temperature Tw4 (t) history. 

B-5

1000 . 

900*' 

800 

700" 

600 : ,= 

4 - T+;3 (exp. 5) 

G•E•O-- hltemp 00 510 140 

500 r ... -, n ... .... 1- -.... " 

0 5 10 15 20 25 30 35 40 

Time (s) 

Fig. B-7. Fuel rod simulator temperature Tw3 (t) history. 

1000- KS RBMK-1500 RELAP5/MOD3.2 

900

700-Laaae T6O- _9OO fC~DD -/ -- - 4 (exp. 5) 

500-- htemp 0 5200405 5 0. _ ... . . . . . . . . .

RFI AP5O/MOD)3.2

0 10 15b 30 6 35 40U
Appendix C

Comparisons between Test Data and RELAP5/MOD3.2 and 

RELAP5/MOD3.2.2GAMMA Base Case Results

C-I
KS RBMK-1500 1~ r-,D P5 2-,__

C 

LLi 

"1.

U

LI)

Time (s)

E

34.0 

J.. 

2 . ý E H H ~e -B ý -h y e e -& • M N . -. 1 3B 8 e e 

2.0 

0.0 - - -. -- r 

0 5 10 15 20 25 30 35 40 Time (s) 

Mass flow rate at the FC inlet 

8.0 KS RBMK-1500 

- (exp.E) EEH3e- (colC) 

-6.0 

4.0 

2.0 

0.0 n n.-n . . .. ..... - n 0 5 10 1 0 i5 C, V0

C) 

J 

0 

C) 

a 

E 

C) 

IMass flow rate at the FC inlet FA rod's wall temperatures Twl-Tw4

Fig. C- 1. Comparisons between test data and RELAP5/MOD3.2 and RELAP5/MOD3.2.2GAMMA predictions for the behaviors of the considered parameter G and rod's wall temperatures Twl-Tw4 in the base case with "motor valve 2r". 

C-2

(exp.! COIc)

FA rod's wall temperatures Tw 1 -Tw4

/un•xo
Pressure P in the lower part of FA

9500000 KS RBMK-1500 _ - S/M/QQ12 

9000000 

08500000 __ 

T8000000 

a7500000 

Q6B• Pin (?op.) 

7000000 - - -

6500000 

0 510 s Y6 25. . 40 Time (S)

Pressure P in the lower part of FA

Pressure drop DP16-4 along FA

400000 KS ROMK-- ELAP51vvazz 

350000 -P- -O 6-4 p.5) 

- DP 6-4( c) 

"3300000 

2!250000- __ _ _-

) 200000 - - 6U "' .aE 

•,5ooooo P-'-_ -__ 

0 .,oooo - ___

5 10 I5 20 25 30 35 40 Time (s)

Pressure drop P 16-4 along FA

Fig. C-2. Comparisons between test data and RELAP5/MOD3.2 and RELAP5/MOD3.2.2GAMMA predictions 

for the behaviors of the considered parameters P and DP16-4 in the base case with "motor valve 2r". 

C-3

L--V
100 K5 RBMK-1500 -ELAP5'QQ32 

900011 _ 

80014 

700 ' 

600 - nm9 

--- TW (exp.5 

5004temp 0 20400 5 

0 i 2o 25 SO 35 40 

Time (s) 

Rod wall temperature TwI (z=6.94 m)

KS RBMK-1500 _ __ _ PAIM'03.2.2 

900 

8001 

600 

500 Tý 240

Time (s)

CL

C) 

E 

aT

Rod wall temperature Tw2 (z=6.82 m) 

1000 KS RBMK-500- RELAPS/M 0032.2 

900

700F 

600 J 

500 •• -T 2 (exp.5 

:,em 0 •203905 

50D^ . ...... l R 

Time (s) 30 40

Rod wall temperature Tw I (z=6.94 m) Rod wall temperature Tw2 (z=6.82 m)

Fig. C-3. Comparisons between test data and RELAP5/MOD3.2 and RELAP5/MOD3.2.2GAMMA predictions for the behaviors of the the rod's wall temperatures TwI and Tw2 in the base case with "motor valve 2r". 

C-4

0. 

E

CL E 

E 

I--

40 5 25
Q 

E 

IQ)

Rod wall temperature Tw3 (z=3.82 m)

4) 

E

Rod wall temperature Tw3 ( z=3.82 m)

E

Rod wall temperature Tw4 (z=1.04 m) 

KS RBMK-1500 RELAP5/MOD3.2.2 

800h 

700 / 

600[jr 

T," 4 (exp. 5) 

B h ,• emp 0q1)5200403 500 ....

5 10 15 T0 ime 40 "Time (s)

Rod wall temperature Tw4 (z=1.04 m)

Fig. C-4. Comparisons between test data and RELAP5/MOD3.2 and RELAP5/MOD3.2.2GAMMA predictions 

for the behaviors of the the rod's wall temperatures Tw3 and Tw4 in the base case with "motor valve 2r".

C-5

0 ^
1OOO- KS RBMK-1500 RELAP5/MOD3.2 

h e- wter 00510 004 Le el 6.94 m - httemp 00510.904 Le el 6.82 m - httemp 00510 404 Le el 3.82 m 

900 600 - httern 00510 404 Le el 1.04 m 

800 

700 .. 

800- . ... . . . . .. . . . . . .. . . .,- • •e

500 

0 50 100 150 200 250 300 .50 40

Time (s) 0

Inner row rod's wall temperatures Tw 1 -Tw4

1000 KS RBMK-1500 _ __ _ 5/MO03.2.2 - htte rn 00510 te e005 e 6.94 m 

- httemp 00510:1905 Le el 6.82 m - hitemp 00510 405 to el 3.82 m 

900 - 0000 - httem 00510 405 Le el 1.04 m 

800 A A , 

700 

600 - _ 

500ý

50 IV 0 U lUU 150 300 350 Time (s) 400

0) 

E 

,T 

I10 - -MO 3.2 S- htte np 005:!04004 evel 6. 4 m ShtI e np 005203904 evel 6. 2 m 

Shtteý np 005& 01404 evel 3.82 m 900 - - - hlenp 005200404 evel 1.14 m 

700-. 

800

0 0 100 150 200 250 30 350 4 

Time (s) 0

Outer row rod's wall temperatures Twl-Tw4

1000 KS RBK 

00--I/

8007 

800 - - httemp 005204)06 Lte 6.94 n 

EKH30- hitemp 005203 06 LtZ 6.82 .1 - htternp 005201 06 Ltey\ 3.82 M 

70(0- httemp 005200 06 LevO 1.04 m 

600 - _ 1- 

500

0) 

a 

0) 

a. 

E 

0) 

H

K-1500 ...AP5/MQD3.2.2

O5 IOU I0O 200 250 Time (s) 300 350 400

Inner row rod's wall temperatures Tw 1 -Tw4

Fig. C-5. Comparisons between RELAP5/MOD3.2 and RELAP5/MOD3.2.2GAMMA predictions for the behaviors of the rod's wall temperatures Twl-Tw4 in the base case with "motor valve 2r". 

C-6

Outer row rod's wall temperatures Tw 1 -Tw4

0) 

00 

E

0) a 

0) 

E 

P)

KS RBMK-1500

0

0
Appendix D 

Comparisons between Test Data and RELAP5IMOD3.2.2GAMMA 

Sensitivity Study Results

D-1
",;ý6.0 

04.0 

2.0

0.0 0

RrM APS/UAfl3 22

KS R(4.K-1O0n

D 1 5 20 

Time (s) 5 4

Mass flow rate G at the FC inlet (motor valve 2r)

8.0 KS RBMK-1500 _ _ _ - P5/MY03.2.2 

- (exp.5 

-e (m coic) 

6.0

4.0

2.0' 

0 5 10 15 20 25 30 35 40

Time (s)

Mass flow rate G at the FC inlet (TDJ)

9500000 ... ..... . ...- __ ., 

9000000

-. 8500000 -,;.j L 

K RBMK0150 

S8000000 -

U 1 20 

Time (s) 5 4

7000000 

6500000-

Pressure P in the lower part of FA(motor valve 2r)

KS ARLAK-ISfi 50 000 _.........- .... I . 

9000000 -.- -

8ooo00 

-7500000 

- Pin (xp.5) GBBEM- Pin (olc) 7000000 

6500000 .... .... ...

10 1I 20 Time (s) 30 32 40

Pressure P in the lower part of FA (TDJ)

Fig. D- 1. Comparisons between test data and RELAP5/MOD3.2.2GAMMA predictions for the behaviors of the 

considered parameters G and P in the cases with "motor valve 2r" and Time Dependent Junction in LWC

D-2

COIc)

Z~~r-. H-3fHE E-B

r 1 flm 1 1 I "'.'I

(4 

0•

801KS RBM IK- 1500

(3{ 4•(•10 --

980I -- -Pin Pin ýýxo.5) o c0

1 5 0 5

0
400000- KS RBMK15 

350000.-o- -DPp6-4 ••5) 

DP-6-4 (IC) 

Cý300000 -- - - ___ ___ 

2500000 - - - -----

e)• 

S200000 • - -64 -e 

-150000

-100000

0 .... 1I74, 1* t r .... 1 ..... i ir

Time (s)

In ,e;A.n09 99

350000 -P- - o_ 6-4 _5) S-DPI 6-4 ( lc ) 

6 300000 - - - - __ __ ___ 

S250000

200000 __ 

Z 150000 

C 

210O000 

S50000 I

15 20 25 30 35 40 Time (s)

6) 

0 

6) 

0

E 6) 

I1000 - -

900 

700 

5 0 

700 z GBE 0 

0 5 10 15 20 25 30 35 4( 

Time (s)

Rod wall temperature Tw 1, z=6.94 m (motor valve 2r)

0. 

E

1000 KS RBMK- 1500 - ELAPS/M)0322 

900 - ___ 

01 

800 

700O -- __ __ 

600 : -

_ -- - T' I (etp 

50 -h lem 0 5204005 

e30 35 4 Time (s)

Rod wall temperature Twl, z=6.94 m (TDJ)

Fig. D-2. Comparisons between test data and RELAP5/MOD3.2.2GAMMA predictions for the behaviors of the considered 

parameters DP16-4 and TwI in the cases with "motor valve 2r" and Time Dependent Junction in LWC. 

D-3

L.

Pressure drop DP16-4 along FA (motor valve 2r)

400000

5 10

Pressure drop DP16-4 along FA (TDJ)

KS R13MK-i5OO - A.1 /-- I ?

0 1-1 ... ..... I r

KS RBMK- 1500 ,'LP5M003.2.2

0 3) . 4 0 1 o 1

J L.

0
900-O 

800 - - _ 

700 

T%,2 (exp 

500 .r r -h ten. 0 20390 

1 10 Is 20 25 30 35 4C Time (s)

Rod wall temperature Tw2, z=6.82 m (motor valve 2r)

1000 KS RBMK-1500 _ - AP51MO03.2.2 

900

800 

700 - __ - -

600 - - - - -eB 

500 G. hi- temp 0 

0 5 10 15 20 25 30 35 0

Time (s)

0. 

Q)1

900

800- 

700-. - _ 

-00- 3 (e-0 

50 ....... .. ýhl temp 0 10 

0 5 10 15 20 25 30 35 4 Time (s)

Rod wall temperature Tw3, z=3.82 m (motor valve 2r)

0 

6) 

0

2 

6)

Rod wall temperature Tw2, z=6.82 m (TDJ)

100 KS RBMK-1500 RELAP5/MOD3.2.2 

900 

800 - _ _ 

700 --- __ 

60 0- - -

- T 3 (exp 500 , ,r h temp 0 510140 . 

0 5 10 15 - 0 26 30 3S 4

Time (s)

Rod wall temperature Tw3, z=3.82 m (TDJ)

Fig. D-3. Comparisons between test data and RELAP5/MOD3.2.2GAMMA predictions for the behaviors of the rod's 

wall temperatures Tw2 and Tw3 in the cases with "motor valve 2r" and Time Dependent Junction in LWC. 

D-4

0 

EE 

f2

KS RSMK-1500 - ... I-- , , KS RBMK-1500 - - A.- ý -

0

1
4,800 

4, 

(1 700 E 

600 

4 T4 (exp. 5004 50 -h .T, em 0 ~20040 6 1 0 15 20 25 30 35 40 

Time (s) 

Rod wall temperature Tw4, z=1.04 m (motor valve 2r) 

... KS R8MlK- 1500 ~A5M0..

4, 

0 

4, 

E 

4, 

I1000' 

900

8O00 

700 

600 - -

6em 0 

T00 4 (.. 

500 RBMK-150 ELAPS D520040

E

1000 KS RBMK-1500 Test 5 RELAP5/MOD3.2.2 

" htemb 0052C; 906 Lf vel 6.82 m 

900 • htteme >02246L••, 0051C 1405 L4 vel 3.8; m 

800 

500 

0 5 10 15 20 25 30 35 40

Time (s) 

FA rod's wall temperatures Tw I -Tw4 (motor valve 2r)

CL 

E 

4,

KS RBMK-1500 Test 1000 936 httem 0052 06 LLeS6.9, m 

6880 htte m 005 3906 L vel 6.8, m &6&6.& httem 0051C1405 L vel 3.8, m .O#W httem 0052CO406 L vel 1.01 

goo-, -14 

600 _____ 

500

0 s b 15 20 25 30 35 40 5 1 o 1 20 25 30 35 40 Time (s) Time (s) 

Rod wall temperature Tw4, z=1.04 m (TDJ) FA rod's wall temperatures Tw 1 -Tw4 (TDJ) 

Fig. D-4. Comparisons between test data and RELAP5/MOD3.2.2GAMMA predictions for the behaviors of the rod's 

wall temperatures Tw4 and Twl-Tw4 in the cases with "motor valve 2r" and Time Dependent Junction in LWC. 

D-5

0
Appendix E 

Base Case RELAP5/MOD3.2 input deck listing

E-1
=ks2 05 test 

*RBMK-1500 Stop Flow Experiment at KS-2 Test Facility 

*Base case input deck listing of KS2-05 test

Assesment of RELAP5/MOD3.2 against KS2-05 test 

Initial conditions 

FA power = 2486.0 kWt 

FA inlet pressure = 8.40 MPa 

FA inlet mass flow = 4.70 kg/s 

FA inlet water temperature = 527.45 K

100 new aransnt 

*0000101 inp-chk 

0000102 sisi 

0000110 nitrogen 

* TIME STEPS CONTROL CARDS 

*crdno time mindt maxdt ssdtt minor major restart 

0000201 1000.0 1.0-6 0.01 15003 500 1000050000 

*0000202 1400. 1.0-6 0.01 15003 200 400004000000 

*0000203 1450. 1.0-6 0.01 15003 10 40000 4000000 

*0000204 1600. 1.0-6 0.01 15003 100 400004000000 

* HIDRODYNAMIC COMPONENTS 

* PUMP I AND PUMP 2 PERFORMANCE DATA 

* Volume = 0.0587 m*m*m 

* rated pump velocity = 314 rad/s 

* rated flow = 0.158 m*m*m/s 

* rated head = 105.4 m 

* rated torque = 782.0 N*m 

* rated density 854.9 .kg/m*m*m 

* moment of inertia = 11.2 kg*m*m 

* actual pump velocity = 314 rad/s 

* PUMP 1, component 71 

0710000 pumpl pump * flow area length volume az inc dz tlpvbfe 

0710101 0.0214 0.0 0.0587 0.0 0.0 0.0 0000000 * from area floss rloss efvcahs 

0710108 0470500020.0 0.1 0.1 0001120 * to area floss rloss efvcahs 

0710109 072010001 0.0 0.1 0.1 0001120 

0710200 103 7.8+6527.45 

0710201 1 0.00 0.0 0.0 

0710202 1 0.00 0.0 0.0 

0710301 0-1 -3 0 0 0 0 * rad/s veloc rflow rhead rtorq inert rdens rmtorq 

0710302 314.0 1.0 0.158 105.4 445.0 11.2 854.9 782.0 0.0 0.0 0.0 0.0 

0716001 0.0 0.0 

0716002 314.01.0 

0716100 0time 

0716101 0.0 314.0 

0716102 500. 314.0 

0716103 4000. 314.0

SINGL PHASE HEAD AND TORQUE CURVES

* head curve no I han 

*crdno curve type curve regime 

0711100 1 1 * flow/rflow head/rhead 

0711101 0.0 1.0700 

0711102 0.3515 1.0721 

0711103 0.5272 1.0816 

0711104 0.7030 1.0721 

0711105 0.8787 1.0436 

0711106 1.0000 1.0000

torque curve no I ban

*crdno curve type 

0711200 2 

* flow/rflow 

0711201 0.0 

0711202 0.3515 

0711203 0.5272 

0711204 0.7030 

0711205 0.8787 

0711206 1.0000

curve regime 

1 

torqle/rtorque 

0.98 

0.693 

0.845 

0.955 

0.994 

1.000

* 

* 

* 

* 

* 

*

E-2

* 

*

* 

*

* Head curve no 2 HVN 

*crdno type regime 

0711300 1 2 

* gnom/g (h/hnom)/(g/gnom)**2 

0711301 0.0 -1.584 

0711302 0.221 -1.056 

0711303 0.442 -0.528 

0711304 0.663 0.0587 

0711305 0.884 0.704 

0711306 1.0 1.00 

* Torque curve no 2 HVN 

*crdno type regime 

0711400 2 2 * gnomlg (mnmnom)/(gfgnom)**2 

0711401 0.0 -1.148 

0711402 0.221 -0.549 

0711403 0.442 -0.075 

0711404 0.663 0.349 

0711405 0.884 0.749 

0711406 1.000 1.000 

* Head curve no 3 HAD 

*crdno type regime 

0711500 1 3 

* g/gnom h/Mmom 

0711501 -1.0 5.5 

0711502 -0.452 3.276 

0711503 -0.362 2.928 

0711504 -0.271 2.658 

0711505 -0.181 2.430 

0711506 -0.0905 2.244 

0711507 0.000 2.058 

* Torque curve no 3 HAD 

*crdno type regime 

0711600 2 3 * gnomng (nWmnom) 

0711601 -1.0 3.64 

0711602 -0.995 3.612 

0711603 -0.905 3.326 

0711604 -0.814 2.96 

0711605 -0.724 2.653 

0711606 -0.633 2.388 

0711607 -0.543 2.133 

0711608 -0.452 1.888 

0711609 -0.362 1.653 

0711610 -0.271 1.449 

0711611 -0.181 1.265 

0711612 -0.0905 1.020 

0711613 0.000 0.980 

* Head curve no 4 HVD 

*crdno type regime 

0711700 1 4 

* gnomlg (h/hnom)/(g/gnom)**2 

0711701 -1.0 5.5 

0711702 -0.884 4.869 

0711703 -0.663 3.755 

0711704 -0.442 2.992 

0711705 -0.221 2A64 

0711707 0.000 2.024 

* Torque curve no4 HVD 

*crdno type regime 

0711800 2 4 

* gnom/g (n/mnom)/(g/gnom)**2
0711801 -1.0 

0711802 -0.884 

0711803 -0.663 

0711804 -0.442 

0711805 -0.221 

0711813 0.000

3.64 

3.343 

2.644 

2.095 

1.746 

1.547

* Head curve no 5 HAT 

*crdno type regime 

0711900 1 5 

* gnornfg (h/hnom) 

0711901 0.0 0.42 

0711902 0.0452 0.426 

0711903 0.0905 0.420 

0711904 0.181 0.444 

0711905 0.271 0.480 

0711906 0.362 0.504 

0711907 0.452 0.552 

0711908 0.543 0.600 

0711909 0.633 0.696 

0711910 0.724 0.828 

0711911 0.814 0.984 

0711912 0.905 1.188 

0711913 1.000 1.360 , 

* Torque curve no 5 HAT 

*crdno type regime 

0712000 2 5 

* gnom/g (m/mnom)/(g/gnom)**2 

0712001 0.0 -0.704 

0712002 0.0452 -0.684 

0712003 0.136 -0.684 

0712004 0.181 -0.612 

0712005 0.271 -0.449 

0712006 0.362 -0.255 

0712007 0.452 -0.122 

0712008 0.543 -0.0306 

0712009 0.633 0.0816 

0712010 0.724 0.224 

0712011 0.814 0.388 

0712012 0.905 0.592 

0712013 0.995 0.776 

0712014 1.000 0.790 * 

* Head curve no 6 HVT 

*crdno type regime 

0712100 1 6 

* gnom/g (h/hnom)/(g/gnom)**2 

0712101 0.0 2.024 

0712102 0.221 1.731 

0712103 0.442 1.525 

0712104 0.663 1.408 

0712105 0.884 1.379 

0712106 1.0 1.36 

* Torque curve no 6 HVT 

*crdno type regime 

0712200 2 6 

* gnom/g (mlmnom)/(g/gnom)**2 

0712201 0.0 1.547 

0712202 0.221 1.397 

0712203 0.442 1.197 

0712204 0.663 1.048 

0712205 0.884 0.848 

0712206 1.000 0.790 

*Head curve no 7 HAR 

*crdno type regime 

0712300 1 7 

* g/gnom h/hnom 

0712301 -1.0 -3.12 

0712302 -0.814 -2.016 

0712303 -0.724 -1.608 

0712304 -0.633 -1.296 

0712305 -0.543 -0.996 

0712306 -0.452 -0.672 

0712307 -0.362 -0.360 

0712308 -0.271 -0.072 

0712309 -0.181 0.216

0712310 -0.0905 

0712311 -0.0452 

0712312 0.000

0.360 

0.408 

0.420

* Torque curve no 7 HAR *crdno type regime 

0712400 2 7 

* gnom/g (m/mnom) 

0712401 -1.0 -4.34 

0712402 -0.814 -3.142 

0712403 -0.724 -2.724 

0712404 -0.543 -2.286 

0712405 -0.452 -1.939 

0712406 -0.362 -1.592 

0712407 -0.271 -1.286 

0712408 -0.181 -1.000 

0712409 -0.0905 -0.796 

0712410 0.000 -0.704 , 

* Head curve no 8 HVR 

*crdno type regime 

0712500 1 8 

* gnom/g (hhnom)/(glgnom)**2 

0712501 -1.0 -3.12 

0712502 -0.884 -2.992 

0712503 -0.663 -2.757 

0712504 -0.442 -2.435 

0712505 -0.221 -2.053 

0712507 0.000 -1.584 . 

* Torque curve no 8 HVR 

*crdno type regime 

0712600 2 8 

* gnonv'g (mmn-om)/(g/gnom)**2 

0712601 -1.0 -4.34 

0712602 -0.884 -3.941 

0712603 -0.663 -3.218 

0712604 -0.442 -2.495 

0712605 -0.221 -1.821 

0712613 0.000 -1.148 

* PUMP 1 DISCHARGE PIPELINE, component v.72 

0720000 disch2 pipe 

0720001 5 

0720101 28.65-3 5 

0720301 1.15 2, 1.85 4, 2.2 5 

0720601 0.0 5 

072080140.0-6 0.1915 

0720901 0.0 0.0 1, 0.10 0.10 2 

0720902 0.0 0.0 3, 0.10 0.10 4 

*crdno tlpvbfe 

0721001 0000000 5 

*crdno efvcahs 

0721101 00010004 

0721201 103 7.8+6 527.45 0.0 0.0 0.0 5 

0721300 1 

07213010.0 0.0 0.04 

* PUMP 2, component 73 

0730000 pump2 pump 

* flow area length volume az inc dz tlpvbfe 

0730101 0.0214 0.0 0.0587 0.0 0.0 0.0 0000000 

* from area floss rloss efvcahs 

0730108 0720500020.0 0.1 0.1 0001120 

* to area floss floss efvcahs 

0730109 0740100010.0 0.1 0.1 0001120 

0730200 103 8.5+6 527.45 

0730201 1 0.00 0.0 0.0 

0730202 1 0.00 0.0 0.0 

0730301 0-1 -3 0 0 0 0 

* rad/s veloc rflow rhead rtorq inert rdens 

0730302 314.0 1.0 0.158 105.4 445.0 11.2 854.9 782.0 0.0 0.0 0.0 0.0

E-3
0736001 0.0 0.0 

0736002 314.0 1.0 

0736100 0 time 

0736101 0.0 314.0 

0736102 500. 314.0 

0736103 4000. 314.0

* 

* 

* 

*

SINGL PHASE HEAD AND TORQUE CURVES 

head curve no I han

*crdno curve type 

0731100 1 

* flow/rflow 

0731101 0.3515 

0731102 0.5272 

0731103 0.7030 

0731104 0.8787 

0731105 1.0000

* 

*

curve regime I 

head/rhead 

1.0721 

1.0816 

1.0721 

1.0436 

1.0000

torque curve no 1 ban

*crdno curve type curve regime 

0731200 2 1 

* flow/rflow torque/rtorque 

0731201 0.0 0.693 

0731202 0.3515 0.693 

0731203 0.5272 0.845 

0731204 0.7030 0.955 

0731205 0.8787 0.994 

0731206 1.0000 1.000 

* Head curve no 2 HVN 

*crdno type regime 

0731300 1 2 

* gnom/g (h/hnom)/(g/gnom)**2 

0731301 0.0 -1.584 

0731302 0.221 -1.056 

0731303 0.442 -0.528 

0731304 0.663 0.0587 

0731305 0.884 0.704 

0731306 1.0 1.00 

* Torque curve no 2 HVN 

*crdno type regime 

0731400 2 2 

* gnom/g (m/rmnom)/(g/gnom)**2 

0731401 0.0 -1.148 

0731402 0.221 -0.549 

0731403 0.442 -0.075 

0731404 0.663 0.349 

0731405 0.884 0.749 

0731406 1.000 1.000 

* Head curveno3 HAD 

*crdno type regime 

0731500 1 3 

* g/gnom h/hnom 

0731501 -1.0 5.5 

0731502 -0.452 3.276 

0731503 -0.362 2.928 

0731504 -0.271 2.658 

0731505 -0.181 2.430 

0731506 -0.0905 2.244 

0731507 0.000 2.058 . 

* Torque curve no 3 HAD 

*crdno type regime 

0731600 2 3 

* gnom/g (mlmnom) 

0731601 -1.0 3.64 

0731602 -0.995 3.612 

0731603 -0.905 3.326 

0731604 -0.814 2.96 

0731605 -0.724 2.653 

0731606 -0.633 2.388 

0731607 -0.543 2.133 

0731608 -0.452 1.888

0731609 -0.362 

0731610 -0.271 

0731611 -0.181 

0731612 -0.0905 

0731613 0.000

1.653 

1.449 

1.265 

1.020 

0.980

* Head curve no 4 HVD 

*crdno type regime 

0731700 1 4 

* gno-/g Mhmon)/(g/gnom)**2 

0731701 -1.0 5.5 

0731702 -0.884 4.869 

0731703 -0.663 3.755 

0731704 -0.442 2.992 

0731705 -0.221 2.464 

0731707 0.000 2.024 

* Torque curve no 4 HVD 

*crdno type regime 

0731800 2 4 

* gnom/g (m/mnom)/(g/gnom)**2 

0731801 -1.0. 3.64 

0731802 -0.884 3.343 

0731803 -0.663 2.644 

0731804 -0.442 2.095 

0731805 -0.221 1.746 

0731813 0.000 1.547 , 

* Head curve no 5 HAT 

*crdno type regime 

0731900 1 5 

* gnom/g (h/hmom) 

0731901 0.0 0.42 

0731902 0.0452 0.426 

0731903 0.0905 0.420 

0731904 0.181 0.444 

0731905 0.271 0.480 

0731906 0.362 0.504 

0731907 0.452 0.552 

0731908 0.543 0.600 

0731909 0.633 0.696 

0731910 0.724 0.828 

0731911 0.814 0.984 

0731912 0.905 1.188 

0731913 1.000 1.360 

* Torque curve no 5 HAT 

*crdno type regime 

0732000 2 5 

* gnom/g (m/mnom)/(g/gnom)**2 

0732001 0.0 -0.704 

0732002 0.0452 -0.684 

0732003 0.136 -0.684 

0732004 0.181 -0.612 

0732005 0.271 -0.449 

0732006 0.362 -0.255 

0732007 0.452 -0.122 

0732008 0.543 -0.0306 

0732009 0.633 0.0816 

0732010 0.724 0.224 

0732011 0.814 0.388 

0732012 0.905 0.592 

0732013 0.995 0.776 

0732014 1.000 0.790 

* Head curve no 6 HVT 

*crdno type regime 

0732100 1 6 

* gnom/g (h/Inom)/(g/gnom)**2 

0732101 0.0 2.024 

0732102 0.221 1.731 

0732103 0.442 1.525 

0732104 0.663 1.408 

0732105 0.884 1.379 

0732106 1.0 1.36 

* Torque curve no 6 HVT 

*crdno type regime 

0732200 2 6

E-4
* gnom/g (m/mnom)/(g/gnom)**2 

0732201 0.0 1.547 

0732202 0.221 1.397 

0732203 0.442 1.197 

0732204 0.663 1.048 

0732205 0.884 0.848 

0732206 1.000 0.790 

* Head curve no 7 HAR 

*crdno type regime 

0732300 1 7 

* g/gnom h/hnom 

0732301 -1.0 -3.12 

0732302 -0.814 -2.016 

0732303 -0.724 -1.608 

0732304 -0.633 -1.296 

0732305 -0.543 -0.996 

0732306 -0.452 -0.672 

0732307 -0.362 -0.360 

0732308 -0.271 -0.072 

0732309 -0.181 0.216 

0732310 -0.0905 0.360 

0732311 -0.0452 0.408 

0732312 0.000 0.420 , 

* Torque curve no 7 HAR 

*crdao type regime 

0732400 2 7 

* gnomlg (ndmnom) 

0732401 -1.0 -4.34 

0732402 -0.814 -3.142 

0732403 -0.724 -2.724 

0732404 -0.543 -2.286 

0732405 -0.452 -1.939 

0732406 -0.362 -1.592 

0732407 -0.271 -1.286 

0732408 -0.181 -1.000 

0732409 -0.0905 -0.796 

0732410 0.000 -0.704 

*Head curve no 8 HVR 

*crdno type regime 

0732500 1 8 

* gnom/g (h/hnom)/(glgnom)**2 

0732501 -1.0 -3.12 

0732502 -0.884 -2.992 

0732503 -0.663 -2.757 

0732504 -0.442 -2.435 

0732505 -0.221 -2.053 

0732507 0.000 -1.584 

* Torque curve no 8 HVR 

*crdno type regime 

0732600 2 8 

* gnom/g (rmnmom)/(gfgnom)*l"2 

0732601 -1.0 -4.34 

0732602 -0.884 -3.941 

0732603 -0.663 -3.218 

0732604 -0.442 -2.495 

0732605 -0.221 -1.821 

0732613 0.000 -1.148 

* PUMP 2 DISCHARGE PIPELINE, component v.74 

0740000 disch2 pipe 

074000110 

0740101 28.65-3 10 

0740301 1.5 2, 2.4 4, 2.0 5, 2.25 9, 1.0 10 

0740601 0.0 10 

0740801 40.0-6 0.191 10 

07409010.0 0.0 1, 0.10 0.10 2 

0740902 0.0 0.0 3, 0.10 0.10 4 

0740903 0.10 0.10 5, 0.0 0.0 8 

0740904 0.10 0.109 

*crdno tlpvbfe 

0741001 0000000 10

*crdno efvcabs 

0741101 00010009 

0741201 103 8.5+6 527.45 0.0 0.0 0.0 10 

0741300 1 

0741301 0.0 0.0 0.0 9 

0750000 sj75 sngljun 

*crdno from to area floss rloss efvcahs 

0750101 0740100001030000000.0 0.0 0.0 0001100 

0750201 1 2.7 0.0 0.0

0760000 sj76 sngljun *crdno from to area floss rloss efvcahs 

0760101 0740100000780000000.0 0.5 0.5 0001100 

0760201 1 5.47 0.0 0.0 

* PUMPS BYPASS, components v.78, valvejun.79, v.80 

0780000 pbypasl pipe 

0780001 8 

0780101 28.65-3 8 

0780301 1.56 1, 1.2 2, 2.9 5, 2.5 6, 1.325 8 

0780601 0.0 8 

0780801 40.0-6 0.191 8 

0780901 0.10 0.10 2, 0.0 0.0 4 

0780902 0.10 0.10 6,0.10 0.10 7 

*crdno tlpvbfe 

0781001 00000008 

*crdno efvcahs 

0781101 00010007 

0781201 103 8.5+6 527.45 0.0 0.0 0.0 8 

0781300 1 

0781301 5.47 0.0 0.07 

* pumps bypass motor valve 28 

0790000 valv28 valve 

*crdno from to area floss rloss efvcahs 

0790101 07801000008000000028.65-3 262.0262.00001100 

0790201 10.00.00.0 

0790300 mtrvlv 

* open close rate initl table 

0790301 428 628 0.0005 1.0 0

438 

538 

628 

428

time0genullO 500.0 n*close 

time Oge null 0 1000.0 n * stop 

438 and -538 n * close 

time 0 ge null 0 9999.0 n * open

0800000 pbypas2 pipe 0800001 7 

0800101 28.65-3 7 

0800301 1.5125 4, 1.6167 7 

0800601 0.07 

080080140.0-60.191 7 

08009010.0 0.0 3, 0.10 0.10 4 

0800902 0.00.0 6 

*crdno tlpvbfe 

0801001 0000000 7 

*crdno efvcahs 

0801101 00010006 

0801201 103 7.65+6 527.45 0.0 0.0 0.0 7 

0801300 1 

0801301 5.47 0.00.0 6

0810000 sjSl sngljun *crdno from to area floss rloss efvcahs 

0810101 080010000 470300020.0 0.5 0.5 0001100 

0810201 15.470.00.0

E-5
* GAS PRESSURIZER, components sj.91, v.92, sj.93, v.94 

0910000 sj91 sngljun *crdno from to area floss rloss efvcahs 

0910101 0410100000920000000.0 0.0 0.0 0001100 

0910201 0 0.0 0.00.0

0920000 

0920001 

0920101 

0920301 

0920601 

0920801 

0920901

surge pipe 

12 

3.14164 12 

1.012 

0.0 12 

6.0-6 0.020 12 

0.0 0.0 11

*crdno t1pvbfe 

0921001 0000000 12 

*crdno efvcahs 

0921101 0001000 11 

0921201 103 7.65+6 527.45 0.0 0.0 0.0 12 

0921300 1 

0921301 0.00.00.0 11 

0930000 sj93 sngljun 

*crdno from to area floss rloss efvcahs 

0930101 0920100000940000000.0 0.0 0.0 0001100 

0930201 0 0.0 0.0 0.0

0940000 gasprz pipe 

0940001 4 

0940101 1.7349-14 

0940301 0.75 4 

0940601 90.04 

0940801 50.0-60.04 

0940901 0.00.03 

*crdno tlpvbfe 

0941001 00000004 

*crdno efvcahs 

0941101 00010003 

0941201 103 7.85+6 527.45 0.00.0 0.0 2 

0941202 0047.85+6527.45 1.0 0.0 0.04 

0941300 1 

0941301 0.00.00.03 

* PRESSURE HEADER, coponents no v. 103, sj 105 * 

1030000 pheader pipe 

1030001 8 

1030101 0.06835 8 

1030301 0.3 8 

1030601 0.08 

1030801 50.0-6 0.295 8 

1030901 0.00.0 7 , 

*crdno tlpvbfe 

1031001 00000008 

*crdno efvcahs 

1031101 00010007 

1031201 103 9.2+6 527.45 0.0 0.0 0.0 8 

1031300 1 

1031301 3.33 0.00.0 7 

1050000 sjlO5sngljun 

*crdno from to area floss rloss efvcahs 

1050101 103010000 106000000 0.0 0.0 0.0 0001100 

1050201 133.33 0.00.0

* BYPASS, component v.106 

1060000 bypass pipe 

1060001 24 

1060101 8.171-3 24

1060301 1.02, 1.5113, 1.34, 1.1374456 

1060302 1.55 7, 1.1425 11, 1.4 13, 1.7 14 

1060303 1.3 15, 1.4 17, 1.7292 22, 0.6 24 

1060601 0.0 2, 90.0 3, 23.0 4, 90.0 6 

10606020.07,90.0 11,0.0 13,0.0 14 

1060603 90.0 15, 0.0 17, 90.0 22, 0.0 24 

1060801 30.0-60.102 24 

1060901 0.0 0.0 1 

1060902 0.15 0.15 4 

* floss rloss constant for valve 5 

1060903 135.0 135.0 5 

1060904 0.15 0.15 7 

1060905 0.0 0.0 10 

1060906 0.15 0.15 11 

1060907 0.0 0.0 12 

1060908 0.15 0.15 14 

1060909 0.0 0.0 15 

10609100.15 0.15 16 

10609110.0 0.0 21 

1060912 0.15 0.15 22 

1060914 0.0 0.0 23 

*crdno tlpvbfe 

10610010000000 24 

*crdno efvcahs 

1061101 000100023 

1061201 103 8.4+6 527.45 0.0 0.0 0.0 24 

1061300 1 

1061301 33.33 0.0 0.023 

1040000 sjl04 sngljun 

*crdno from to area floss rloss efvcahs 

1040101 1030500030010100010.0 0.5 0.5 0001100 

1040201 1 3.9 0.0 0.0 

* GROUP DISTRIBUTION HEADER AND LOWER WATER 

* COMMUNICATION, components v.l,valvejun.2, v.3 

0010000 gdh pipe 

0010001 4 

0010101 3.32-34 

0010301 0.5 1,0.95 3,0.804 

0010601 0.0 1, 90.0 3,0.04 

0010801 20.0-6 0.065 4 

0010901 0.5 0.5 1, 0.0 0.0 2,0.5 0.5 3 

*crdno tlpvbfe 

0011001 00000004 

*crdno efvcahs 

0011101 00010003 

0011201 1039.2+6527.450.00.00.04 

0011300 1 

0011301 3.9 0.0 0.0 3 

* isolating control valve 2r 

0020000 valv2r valve 

*crdno from to area floss rloss efvcahs 

0020101 001010000 003000000 3.3183-3 770.0 770.0 0001100 

0020201 1 3.9 0.0 0.0 

0020300 mtrvlv 

* open close rate initl table 

0020301 702 602 0.25 1.0 0

412 

512 

602 

403 

503 

702

time 0 ge null 0 1400.5 n * close 

time 0 ge null 0 1406.0 n * stop 

412 and -512 n * close 

time 0 ge null 0 1410.00 n * open 

time 0 ge null 0 1410.12 n * stop 

403 and -503 n * open

* lower water communication

E-6
0030000 lwc pipe 

0030001 7 

0030101 3.3183-3 7 

0030301 0.8 1, 1.7 2, 1.775 4, 1.6 5,0.85 7 

0030601 0.0 1, -90.0 2, 0.0 4, 90.0 5, 0.0 7 

0030801 20.0-6 0.065 7 

0030901 0.5 0.5 2, 0.0 0.0 3, 0.5 0.5 6 , 

*crdno tlpvbfe 

0031001 0000000 7 

*crdno efvcahs 

0031101 00010006 

0031201 103 8.40+6 527.45 0.0 0.0 0.0 7 

0031300 1 

0031301 0.00.00.06 

0040000 sj4 sngljun 

*crdno from to area floss floss efvcahs 

0040101 0030100000050100030.0 0.5 0.5 0001100 

0040201 1 3.9 0.0 0.0 

* FUEL CHANNEL WITH FUEL ASSEMBLY, component v.5 

0050000 fuelchn pipe 

0050001 45 

0050101 0.002273 1, 0.002273 41, 0.002273 45 

0050301 0.578 1,0.162,0.36 11,0.1241 

0050302 0.13143, 0.098 44, 0.145 

0050601 90.045 

0050801 4.0-5 8.563-3 45 

0050901 0.0 0.0 1,0.55 0.55 10 

0050902 0.91 0.91 11,0.28 0.28 13 

0050903 0.91 0.91 14,0.28 0.28 16 

0050904 0.91 0.91 17,0.28 0.28 19 

0050905 0.91 0.91 20,0.28 0.28 22 

0050906 0.91 0.91 23,0.28 0.28 25 

0050907 0.91 0.91 26,0.28 0.28 28 

0050908 0.91 0.91 29,0.280.2831 

0050909 0.91 0.91 32,0.28 0.28 34 

0050910 0.91 0.91 35,0.28 0.28 37 

0050911 0.91 0.91 38,0.280.2840 

0050912 0.91 0.91 41,0.0 0.0 43, 0.55 0.55 44 

*crdno tlpvbfe 

0051001 0000100 45 

*crdno efvcahs 

0051101 000100044 

*0051101 010100044 

0051201 102 8.40+6 0.12 0.0 0.0 0.045 

0051300 1 

0051301 3.90.00.044 

0060000 sj6 sngljun 

*crdno from to area floss floss efvcahs 

0060101 0054400030070000000.0 1.74 1.74 0001100 

0060201 1 3.9 0.0 0.0 

* LIFTING PATH WITH FA SUSPENTION, component v.7 

0070000 lftpath pipe 

0070001 11 

0070101 0.00418544 

0070102 0.00721 7, 0.00488 8, 0.0076 11 

0070301 0.38 1, 0.35 2, 0.7975 3, 0.795 4 

0070302 1.6357, 1.07 8,0.689,0.1 10,0.24 11 

0070601 0.0 1,45.02,90.0 11 

0070801 25.0-6 0.073 4 

0070802 20.0-6 0.067 7, 4.0-6 0.0299 8, 4.0-6 0.05288 11 

0070901 0.070.072 

0070902 0.000.003 

0070903 0.500.204 

0070904 0.000.006

0070905 0.160.247 

0070906 0.240.168 

0070907 0.0 0.0 10 

*crdno tlpvbfe 

0071001 000000011 

*crdno efvcahs 

0071101 000100010 

*0071101 0101000 10 

0071201 102 8.0+6 0.120.00.00.011 

0071300 1 

0071301 3.9 0.00.0 10 

0080000 sj8 sngljun 

*crdno from to area floss rloss efvcahs 

0080101 007100003009000000O0.0 0.5 0.5 0001100 

0080201 1 3.9 0.0 0.0 

* STEAM WATER COMMUNICATION, component v.9

0090000 

0090001 

0090101 

0090301 

0090302 

0090303 

0090601 

0090801 

0090901 

0090902 

0090904 

0090905 

0090908 

0090909 

0090910

swc pipe 20 

3.3183-320 

0.75 2,0.6 3, 1.375 5,0.8 6, 1.3 7 

1A 8,0.8 9,2.15 10,2.2615 

1.7175 17,2.3 18,0.7 19,0.5 20 

0.72 19,90.0 20 

20.0-6 0.065 20 

0.5 0.5 3 

0.0 0.0 4 

0.5 0.5 9 

0.0 0.0 14 

0.5 0.5 15 

0.0 0.0 16 

0.5 0.5 19

*crdno tlpvbfe 0091001 0000000 20 

*crdno efvcahs 

0091101 0001000 19 

*0091101 0101000 19 

0091201 1028.0+60.11 0.0 0.0 0.0 20 

0091300 1 

0091301 3.9 0.0 0.0 19 

* UPPER HEADER, components branch 10, v. 11 

0100O00 dcclil branch 

0100001 3 1 

0100101 0.06835 0.7 0.0 0.0 0.0 0.0 4.0-5 0.295 0000000 

0100200 003 8.0+6 527.45 

0101101 010010003009200002 0.00331830.00.0 0001000 

0101201 0.0 0.0 0.0 

0102101 010010002011010001 0.0 0.0 0.0 0001000 

0102201 0.0 0.0 0.0 

0103101 106010000010010001 0.0 0.0 0.0 0001000 

0103201 0.0 0.0 0.0 

011000 upphdr pipe 

0110001 5 

011010168.35-3 5 

0110301 0.74, 0.9 5 

0110601 3.0 5 

011080150.0-60.295 5 

01109010.0 0.04 

*crdno tlpvbfe 

0111001 00000005 

*crdno efvcahs 

0111101 00010004 

0111201 103 8.0+6 539.0 0.0 0.0 0.0 5 

01113001 

0111301 37.23 0.0 0.04 

0120000 sj 12 sngljun

E-7
*crdno from to area floss rloss efvcahs 

0120101 011050003 014010001 0.0 0.5 0.5 0001100 

0120201 10.0 0.0 0.0 

* STEAM WATER PIPELINE, component v.14 

0140000 swpline pipe 

0140001 8 

0140101 7.7-3 8 

0140301 0.9 1,1.02, 1.33, 1.54,0.85 

0140302 1.0 6, 1.5 7,0.5 8 

0140601 90.0 1,0.08 

0140801 30.0-6 0.099 8 

0140901 0.150.157 

*crdno tlpvbfe 

0141001 0000000 8 

*crdno efvcahs 

0141101 00010007 , 

0141201 102 8.0+6 0.05 0.0 0.0 0.0 8 

0141300 1 

0141301 0.00.00.07 

0150000 sjl5sngljun *crdno from to area floss rloss efvcahs 

0150101 0140100000200300030.0 0.0 0.0 0001100 

0150201 0 0.0 0.0 0.0 

* SEPARATOR (ic,2c,3c), component v.20 

0200000 seprt pipe 

0200001 6 

0200101 78.87-3 6 

0200301 0.52,0.73,0.55,0.46 

0200601 90.06 

0200801 50.0-6 0.317 6 

*crdno tlpvbfe 

0201001 0000000 6 

*crdno efvcahs 

0201101 0001000 5 

0201201 102 8.0+6 0.03 0.0 0.0 0.0 6 

0201300 1 

0201301 0.0 0.00.0 5 

0210000 sj21 sngljun *crdno from to area floss rloss efvcahs 

0210101 0200000000220000000.0 0.0 0.0 0001100 

0210201 0 0.0 0.00.0 

"* AFTER SEPARATOR WATER DOWNCOMER, component v.22, "* valve jun.23, v.25, sj.26 

0220000 downcm22 pipe 

0220001 14 

0220101 8.171-3 14 

0220301 1.152, 1.054, 1.425 6, 1.2 10, 1.325 12 

0220302 1.3 13, 1.275 14 

0220601 -90.0 2, 0.0 6, -90.0 10, 0.0 12 

0220602 -90.0 14 

0220801 30.0-6 0.102 14 

0220901 0.00.0 1,0.150.152 

0220902 0.0 0.0 3, 0.15 0.154 

0220903 0.00.0 5,0.15 0.15 6 

0220904 0.00.09,0.150.15 60 

0220905 0.00.0 11,0.150.15 13 

*crdno tlpvbfe 

0221001 0000000 14 

*crdno efvcahs 

0221101 0001000 13 

0221201 102 8.0+6 0.01 0.0 0.0 0.0 14 

0221300 1 

0221301 0.0 0.0 0.0 13

* after separator water downcomer motor valve 22 

0230000 valv22 valve 

*crdno from to area floss rloss efvcahs 

0230101 0220100000250000008.171-3400.0400.0 0001100 

0230201 1 0.0 0.0 0.0 

0230300 mtrvlv 

* open close rate initl table 

0230301 422 622 0.001 1.0 0 . 

432 time 0 ge null 0 500.0 n * close 532 time 0 ge null 0 1000.0 n * stop 

622 432 and -532 n * close 

422 time 0 ge null 0 9999.0 n * open 

0250000 downcm25 pipe 

0250001 2 

0250101 8.171-3 2 

0250301 0.63752 

0250601 -90.02 

0250801 30.0-6 0.099 2 . 

0250901 0.0 0.0 1 

*crdno tlpvbfe 

0251001 0000000 2 

*crdno efvcahs 

0251101 0001000 1 

0251201 102 8.0+6 0.010.00.0 0.0 2 

0251300 1 

0251301 0.0 0.0 0.0 1 

0260000 sj26 sngljun 

*crdno from to area floss rloss efvcahs 

0260101 0250100000240000000.0 0.0 0.0 0001100 

0260201 00.0 0.0 0.0 

* AFIERCOOLER (70,8t), component v.24 

0240000 cooler pipe * 96 annulus (tube inside tube) 

0240001 4 

0240101 6.5563-34 

0240301 0.2754 

0240601 -90.04 

0240801 4.0-6 0.003 4 

*crdno tipvbfe 

0241001 0000000 4 

*crdno efvcahs 

0241101 0001000 3 

0241201 1027.5+60.010.00.00.04 

0241300 1 

0241301 0.00.00.03 

0270000 sj27 sngljun 

*crdno from to area floss floss efvcahs 

0270101 0240100000280000000.0 0.0 0.0 0001100 

0270201 0 0.00.0 0.0 

* AFTERCOOLER WATER DOWNCOMER, components v.28, sj.29 

0280000 downcm28 pipe 

0280001 6 

0280101 8.171-36 

0280301 0.95 2, 1.075 4, 1.215 6 

0280601 -90.06 

0280801 30.0-60.1026 

0280901 0.0 0.0 1,0.15 0.15 2, 0.0 0.0 5 

*crdno tlpvbfe 

0281001 0000000 6 

*crdno efvcahs 

0281101 01010005 , 

0281201 1037.3+6527.450.00.00.06 

0281300 1 

0281301 0.00.00.05

E-8
0290000 sj29 sngljun *crdno from to area floss floss efvcahs 

0290101 0280100000410500030.0 0.0 0.0 0001100 

0290201 0 0.0 0.0 0.0 

* AFTER SEPARATOR STEAM PIPELINE, components sj.36, v.30, 

0360000 sj36 sngljun *crdno from to area floss rloss efvcahs 

0360101 0200100000300000000.0 0.0 0.0 0101100 

0360201 00.00.00.0 

0300000 steam pipe 

0300001 12 

0300101 8.171-3 12 

0300301 0.6 1,0.8 2,0.7 3,0.954 

0300302 1.4756, 1.47, 1.7 8,0.759 

0300303 0.65 10,0.75 12 

0300601 90.0 1, 0.0 6, -45.0 7, 0.0 10, -90.0 12 

0300801 30.0-60.102 12 

0300901 0.150.15 1,0.00.04 

0300902 0.00.05,0.150.15 10,0.00.0 11 

*crdno tlpvbfe 

0301001 0000000 12 

*crdno efvcahs 

0301101 0001000 11 

0301201 1028.0+60.03 0.0 0.0 0.0 12 

0301300 1 

0301301 0.00.00.0 11 

* after separator steam downcomer motor valve 19 

0310000 valvl9 valve 

*chino from to area floss floss efvcahs 

0310101 030010000 032000000 8.171-3400.0400.0 0001100 

0310201 1 0.0 0.0 0.0 

0310300 mtrvlv 

* open close rate initi table 

0310301 419 619 0.001 1.0 0 . 

439 time 0 ge null 0 500.0 n * close 

539 time 0ge nullO0 1000.0On *stop 

619 439 and -539 n * close 

419 time 0 ge null 0 9999.0 n * open 

* CONDENSER (lk,2k3k), component v.32 

. 

0320000 condens pipe * bundle of 72 U-tubes 

0320001 4 

0320101 81.804-3 4 

0320301 0.60625 4 

0320601 -90.04 

0320801 4.0-646.73-3 4 

*crdno tlpvbfe 

0321001 00001004 "*0321001 0000000 4 

*crdno efvcahs 

0321101 00010003 

0321201 102 7.9+6 0.03 0.0 0.0 0.0 4 

0321300 1 

0321301 0.00.00.03 

0330000 sj33 sngljun 

*crdno from to area floss rloss efvcahs 

0330101 0320100000340000000.0 0.5 0.5 0001100 

0330201 0 0.0 0.0 0.0 

* AFTER CONDENSER WATER DOWNCOMER, component v.34 

0340000 downcm34 pipe 

0340001 15 

0340101 8.171-3 15

0340301 0.85 1, 1.72,0.853,2.04, 1.75 

0340302 1.843 8,2.4 9, 1.85 11, 

0340303 2.26725 12,2.11625 13, 1.85125 15 

0340601 0.0 1, -90.0 2, 0.0 3, -90.04,0.0 5 

0340602 -90.08,0.0 11,-90.0 15 

0340801 30.0-6 0.102 15 

0340901 0.15 0.15 6,0.0 0.0 8 

0340902 0.150.15 9,0.00.0 10 

0340903 0.15 0.15 11,0.00.0 12 

0340904 0.15 0.15 13,0.00.0 14 

*crdno tlpvbfe 

0341001 0000000 15 

*crdno efvcahs 

0341101 0001000 14 

0341201 103 7.9+6 527.45 0.0 0.0 0.0 15 

0341300 1 

0341301 0.00.00.0 14 

0350000 sj35 sngljun 

*crdno from to area floss rloss efvcahs 

0350101 034010000 041040003 0.0 0.0 0.0 0001100 

0350201 0 0.0 0.0 0.0 

* FIRST INTAKE HEADER, component v.41 

, 

0410000 inthdrl pipe 

0410001 7 

04101010.02865 7 

04103010.5 1, 1.00 6, 0.57 

04106010.0 7 

0410701 0.07 

0410801 40.0-6 0.191 7 

04109010.0 0.0 6 , 

*crdno tlpvbfe 

0411001 0000000 7 

*crdno efvcahs 

0411101 0001000 6 

0411201 103 7.9+6 527.45 0.0 0.0 0.0 7 

0411300 1 

04113010.0 0.0 0.0 6 

* MECHANICAL FILTERS, components sj.42, sj.43, sj.44 

0420000 sj42 sngljun 

*crdno from to area floss floss efvcahs 

0420101 041040004 045010003 6.6476-3 140.0 140.0 0001100 

0420201 00.0 0.0 0.0 

0430000 sj43 sngljun 

"*crdno from to area floss rloss efvcahs 

0430101 041050004 045020003 6.6476-3 140.0 140.0 0001100 

0430201 0 0.00.0 0.0 

0440000 sj44 sngijun 

*crdno from to area floss rloss efvcahs 

0440101 041060004 045030003 6.6476-3 140.0 140.0 0001100 

0440201 0 0.0 0.0 0.0 

* SECOND INTAKE HEADER, component v.45 

0450000 inthdr2 pipe 

0450001 3 

0450101 0.02865 3 

0450301 1.00 2, 1.35 3 

0450601 0.0 3 

0450801 40.0-6 0.191 3 

0450901 0.0 0.0 2 

*crdno tlpvbfe 

0451001 0000000 3 

*crdno efvcahs 

0451101 00010002

E-9
0451201 103 7.5+6 527.45 0.0 0.0 0.0 3 

0451300 1 

0451301 0.0 0.0 0.0 2 

0460000 sj46 sngljun 

*crdno from to area floss rloss efvcahs 

0460101 0450100040470000000.0 0.0 0.0 0001100 

0460201 00.00.00.0 

1000000 calch tnidpvol 

1000101 0.0 2.0 2.0 0.0 0.0 0.0 1.0-6 0.0 0 

1000200 103 

1000201 0.07.85+6 527.45 

1010000 sjlOl sngljun 

*crdno from to area floss floss efvcahs 

1010101 1000000000450000000.0 0.0 0.0 0001100 

1010201 00.0 0.0 0.0

*1010000 inventor tmdpjun 

*1010101 1000000000450000000.0 

*1010200 1 

*1010201 0.00.000.0 0.0 

* PUMP I SUCTION PIPELINE, component v.47 , 

0470000 suctnm pipe 

0470001 5 

0470101 28.65-3 5 

0470301 1.95 2, 2.14, 2.2 5 * check 2.2 height for subvol 5 

0470601 0.0 5 

047080140.0-6 0.191 5 

04709010.0 0.0 1, 0.10 0.10 2 

0470902 0.0 0.0 3, 0.10 0.10 4 

*crdno tlpvbfe 

0471001 0000000 5 

*crdno efvcahs 

0471101 00010004 

0471201 103 7.5+6 527.45 0.0 0.0 0.0 5 

0471300 1 

04713010.0 0.0 0.04 

"* DOWNCOMER PAST SEPARATORS AND CONDENSERS, 

"* components sj.51, v.52 

0510000 sjSl sngijun *crdno from to area floss floss efvcahs 

0510101 0110500030520100010.0 0.0 0.0 0001100 

0510201 00.00.00.0 

0520000 downcm52 pipe 

0520001 14 

0520101 16.06-3 14 

0520301 1.663 3, 2.2 4, 1.9 5, 1.6 6, 1.5 8 

0520302 1.99,2.45 10, 1.5 11,2.091 12,2.275 14 

0520601 -90.0 3, 0.0 4, -90.0 5, 0.0 6, -90.0 8 

0520602 0.0 9, -90.0 10, 0.0 11, -90.0 14 

0520801 35.0-6 0.143 14 

0520901 0.0 0.0 2,0.15 0.15 6 

0520902 0.0 0.0 7,0.15 0.15 10 

0520903 0.150.15 11 

0520904 0.0 0.0 13 , 

*crdno tlpvbfe 

0521001 0000000 14 

*cdlno efvcahs 

0521101 0001000 13 

0521201 103 8.0+6 538.0 0.0 0.0 0.0 14 

0521300 1

0521301 0.00.00.0 13 

*past separators and condensers downcomer motor valve 29 

0530000 valv29 valve 

*prdno from to area floss rloss efvcahs 

0530101 052010000 041030003 16.06-3 1900.0 1900.0 0001100 

0530201 1 0.0 0.0 0.0 

0530300 mtrvlv 

* open close rate initl table 

0530301 429 629 0.001 1.0 0 

449 time 0 ge null 0 500.0 n * close 

549 time 0 ge null 0 1O00.O n * stop 

629 449 and -549 n * close 

429 time 0 ge null 0 9999. n * open 

* DOWNCOMER FROM UPPER HEADER TO HEAT 

EXCHANGERS (5t,6t), * components sj.61, v.62 

0610000 sj6l sngljun 

*crdno from to area floss rloss efvcahs 

0610101 052060001062000000 0.0 0.0 0.0 0001100 

0610201 00.00.00.0 

0620000 downcm62 pipe 

0620001 8 

0620101 16.06-3 8 

0620301 1.723, 1.3754, 1.355, 1.3256, 1.27, 1.28 

0620601 0.0 3, -90.0 4, 0.0 5, -90.0 6, 0.0 7, -90.0 8 

0620801 35.0-6 0.143 8 

0620901 0.0 0.0 2,0.15 0.15 7 

*crdno tlpvbfe 

0621001 0000000 8 

*crdno efvcahs 

0621101 00010007 

0621201 103 8.0+6 538.00.00.00.08 

0621300 1 

0621301 0.00.00.07 

* heat exchanger downcomer motor valve 14 

0630000 valvl4 valve 

*crdno from to area floss floss efvcahs 

0630101 062010000 064000000 16.06-3 1550.0 1550.0 0001100 

0630201 1 0.00.0 0.0 

0630300 mtrvlv 

* open close rate initl table 

0630301 414 614 0.001 1.0 0 

4 

424 time 0 ge null 0 500.0 n * close 524 time Oge nullO0 1000.0On *sto'p 

614 424 and -524 n * close 

414 time 0 ge null 0 9999.0 n * open

* HEAT EXCHANGER (5t, 6t), component v.64 * 

0640000 htexch pipe * bundle of 48 U-tubes 

0640001 4 

0640101 54.536-3 4 

0640301 0.60625 4 

0640601 -90.04 

0640801 4.0-645.09-3 4 

*crdno tlpvbfe 

0641001 0000100 4 

*crdno efvcahs 

0641101 00010003 

0641201 103 7.5+6 538.0 0.0 0.0 0.04 

0641300 1 

0641301 0.0 0.0 0.0 3 

0650000 sj65 sngljun 

*crdno from to area floss rloss efvcahs

E-10
0650101 0640100000660000000.0 0.0 0.0 0001100 

0650201 00.0 0.0 0.0 

* AFIER HEAT EXCHANGERER DOWNCOMER, component v.66 

0660000 downcm66 pipe 

0660001 9 

0660101 0.0160609 

0660301 1.642 3, 1.649 4, 2.725 5, 2.637 7, 2.0585 9 

0660601 0.0 3, -90.0 4, 0.0 7, -90.0 9 

0660801 35.0-60.143 9 

0660901 0.00.02,0.150.154,0.00.06,0.150.158 

*crdno tlpvbfe 

0661001 00000009 

*crdno efvcahs 

0661101 00010008 

0661201 103 7.5+6 527A5 0.0 0.0 0.0 9 

0661300 1 

0661301 0.00.00.08 

0670000 sj67 sngljun *crdno from to area floss dloss efvcahs 

0670101 0660100000410000000.0 0.0 0.0 0001100 

0670201 0 0.00.0 0.0 

t 

* SECOND CIRCUIT 

2010000 tdv201 tmdpvol 

2010101 0.0 2.0 2.0 0.0 0.0 0.0 1.0-6 0.0 0 

2010200 103 

2010201 0.0 7.5+6 481.0 

2020000 regul tmdpjun 

2020101 201000000 203000000 0.0 

2020200 1 

2020201 0.0 9.50 0.0 0.0 

2030000 htexch pipe * heat exchanger 5t,6t (bundle of 48 U-tubes) 

2030001 8 

2030101 3.768-38 

2030301 0.606258 

2030601 90.04,-90.08 

2030801 2.0-60.01 8 

2030901 0.00.07 

*crdno dpvbfe 

2031001 0000000 8 

*crdno efvcahs 

2031101 00010007 

2031201 103 7.0+6 485.0 0.0 0.0 0.0 8 

2031300 1 

2031301 0.00.00.07 

2040000 sj204 sngljun 

2040101 203010000 205000000 0.0 0.0 0.0 001100 

2040201 00.00.00.0 . 

2050000 tdv2O5 tmdpvol 

2050101 0.0 2.0 2.0 0.0 0.0 0.0 1.0-6 0.0 0 

2050200 103 

2050201 0.0 7.0+6 500.0 

10641000 82200.005 

10641100 01 

10641101 10.0065 

10641201 11 

10641301 0. 1 

10641401 507.02 

10641501 203010000 10000 1 1 29.1 8 

10641601 064040000-10000110 129.14 

10641602 064010000 10000 110 129.18 

10641701 0 0.0 0.0 0.0 8 

10641801 0.0 20.0 20.0 0.0 0.0 0.0 0.0 1.0 8 

10641901 0.0 20.0 20.0 0.0 0.0 0.0 0.0 1.0 8

2110000 tdv21 Itmdpvol 

2110101 0.0 2.0 2.0 0.0 0.0 0.0 1.0-6 0.0 0 

2110200 103 

2110201 0.0 7.5+6481.0 

2120000 regul tmdpjun 

2120101 211000000 214000000 0.0 

2120200 1 

2120201 0.0 9.50 0.0 0.0 

2140000 htexch pipe * aftercooler 7t,8t (tube inside tube) 

2140001 8 

2140101 3.768-3 8 

2140301 0.275 8 

2140601 90.04,-90.08 

2140801 2.0-60.01 8 

2140901 0.00.07 * 

*crdno tlpvbfe 

2141001 0000000 8 

*crdno efvcahs 

2141101 00010007 

2141201 103 7.0+6 485.0 0.0 0.0 0.0 8 

2141300 1 

2141301 0.00.00.07 

2150000 sj215 sngljun 

2150101 2140100002160000000.00.0 0.0 001100 

2150201 00.0 0.0 0.0 

2160000 tdv2l6 tmdpvol 

2160101 0.0 2.0 2.0 0.0 0.0 0.0 1.0-6 0.00 

2160200 103 

2160201 0.07.0+6500.0 

10241000 82200.005 

10241100 01 

10241101 10.0065 

10241201 1 1 

10241301 0. 1 

10241401 507.02 

10241501 214010000 10000 1 113.28 

10241601 024040000-10000 110 1 13.24 

10241602 024010000 10000 110 113.2 8 

10241701 00.00.0 0.08 

10241801 0.0 20.0 20.0 0.0 0.0 0.0 0.0 1.0 8 

10241901 0.0 20.0 20.0 0.0 0.0 0.0 0.0 1.08 

2210000 tdv221 tmdpvol 

2210101 0.0 2.0 2.0 0.0 0.0 0.0 1.0-6 0.0 0 

2210200 103 

2210201 0.0 7.5+6481.0 

2220000 regul tmdpjun 

2220101 221000000 224000000 0.0 

2220200 1 

2220201 0.0 14.3 0.0 0.0 

2240000 condens pipe * condenser Ik,2k,3k (bundle of 72 U-tubes) 

2240001 8 

2240101 5.652-3 8 

2240301 0.0625 8 

2240601 90.04,-90.08 

2240801 2.0-60.018 

2240901 0.00.07 

*crdno tlpvbfe 

2241001 0000000 8 

*crdno efvcahs 

2241101 00010007 

2241201 103 7.0+6 485.0 0.0 0.0 0.0 8 

2241300 1 

2241301 0.00.0 0.0 7 

2250000 sj225 sngljun

E-11
2250101 2240100002260000000.00.0 0.0 001100 

2250201 00.00.00.0 

2260000 tdv226 trmdpvol 

2260101 0.0 2.0 2.0 0.0 0.0 0.0 1.0-6 0.0 0 

2260200 103 

2260201 0.0 7.0+6 500.0 

10321000 82200.005 

10321100 01 

10321101 10.0065 

10321201 11 

10321301 0. 1 

10321401 507.02 

10321501 224010000 10000 1 143.65 8 

10321601 032040000-10000 110 143.654 

10321602 032010000 10000110 143.658 

10321701 00.00.0 0.08 

10321801 0.0 20.0 20.0 0.0 0.0 0.0 0.0 1.08 

10321901 0.0 20.0 20.0 0.0 0.0 0.0 0.0 1.0 8 

HEAT STRUCTURES 

20800001 httemp 005100104 

20800002 httemp 005100204 

20800003 htemp 005100304 

20800004 huemp 005100404 

20800005 huemp 005100504 

20800006 httemp 005100604 

20800007 httemp 005100704 

20800008 httemp 005100804 

20800009 httemp 005100904 

20800010 httemp 005101004 

20800011 httemp 005101104 

20800012 httemp 005101204 

20800013 httemp 005101304 

20800014 httemp 005101404 

20800015 httemp 005101504 

20800016 httemp 005101604 

20800017 httemp 005101704 

20800818 httemp 005101804 

20800919 httemp 005101904 

20800020 httemp 005102004 

20800021 httemp 005102104 

20800022 httemp 005102204 

20800023 httemp 005102304 

20800024 httemp 005102404 

20800025 httemp 005102504 

20800026 httemp 005102604 

20800027 httemp 005102704 

20800028 hutemp 005102804 

20800029 httemp 005102904 

20800030 httemp 005103004 

20800031 httemp 005103104 

20800032 httemp 005103204 

20800033 httemp 005103304 

20800034 httemp 005103404 

20800035 httemp 005103504 

20800036 htiemp 005103604 

20800037 httemp 005103704 

20800038 httemp 005103804 

20800039 httemp 005103904 

20800040 httemp 005104004 

20800041 httemp 005200104 

20800042 httemp 005200204 

20800043 httemp 005200304 

20800044 httemp 005200404 

20800045 httemp 005200504 

20800046 httemp 005200604 

20800047 httemp 005200704 

20800048 httemp 005200804 

20800049 httemp 005200904 

20800050 httemp 005201004 

20800051 httemp 005201104 

20800052 httemp 005201204 

20800053 httemp 005201304 

20800054 httemp 005201404

20800055 httemp 005201504 

20800056 httemp 005201604 

20800057 httemp 005201704 

20800858 httemp 005201804 

20800959 httemp 005201904 

20800060 httemp 005202004 

20800061 httemp 005202104 

20800062 httemp 005202204 

20800063 httemp 005202304 

20800064 httemp 005202404 

20800065 httemp 005202504 

20800066 httemp 005202604 

20800067 httemp 005202704 

20800068 httemp 005202804 

20800069 httemp 005202904 

20800070 httemp 005203004 

20800071 httemp 005203104 

20800072 httemp 005203204 

20800073 httemp 005203304 

20800074 httemp 005203404 

20800075 httemp 005203504 

20800076 httemp 005203604 

20800077 httemp 005203704 

20800078 httemp 005203804 

20800079 httemp 005203904 

20800080 httemp 005204004 

20800081 vgjj 005410000 

20800082 dt 0 

20800083 cputime 0 

20800084 dtcmt 0

* 

*

fuel channel

*10051000 

*10051100 

*10051101 

*10051102 

*10051103 

*10051201 

*10051301 

*10051401 

10051000 

10051100 

10051101 

10051102 

10051201 

10051301 

10051401 

10051501 

10051502 

10051503 

10051601 

10051602 

10051603 

10051701 

10051702 

10051703 

10051900 

10051901 

10051902 

10051903 

10051904 

10051905 

10051906 

10051907 

10051908 

10051909 

10051910 

10051911 

10051912 

10051913 

10051914 

10051915 

10051916 

10051917 

10051918 

10051919 

10051920

40 13 2 00.00375 

01 

1 0.004 1 0.00425 1 0.0045 1 0.00475 

1 0.005 1 0.00525 1 0.0055 1 0.00575 

1 0.006 1 0.00625 1 0.0065 1 0.00675 

112 

1.12 

527.3 13 

405 2 00.00375 

01 

1 0.004 1 0.005 

1 0.006 1 0.00675 

14

1.4 

527.3 5 

000 1 0.96 1 

00012.1610 

000 1 0.7240 

005020000 10000 110 10.96 1 

005030000 10000 110 12.16 10 

005120000 10000 110 10.7240 

001 0.006689523559 0.0 0.0 1 

001 0.015051428446 0.0 0.0 10 

0010.005017142815 0.0 0.0 40 1 

0.03576 0.08 5.92 0.08 0.08 0.55 0.55 1.0 0.16 1.222 1.0 1 

0.03576 0.34 6.66 0.18 0.18 0.55 0.55 1.0 0.36 1.222 1.0 2 

0.03576 0.70 6.30 0.18 0.18 0.55 0.55 1.0 0.36 1.222 1.0 3 

0.03576 1.06 5.94 0.18 0.18 0.55 0.55 1.0 0.36 1.222 1.0 4 

0.03576 1.42 5.58 0.18 0.18 0.55 0.55 1.0 0.36 1.222 1.0 5 

0.03576 1.78 5.22 0.18 0.18 0.55 0.55 1.0 0.36 1.222 1.0 6 

0.03576 2.14 4.86 0.18 0.18 0.55 0.55 1.0 0.36 1.222 1.0 7 

0.03576 2.50 4.50 0.18 0.18 0.55 0.55 1.0 0.36 1.222 1.0 8 

0.03576 2.86 4.14 0.18 0.18 0.55 0.55 1.0 0.36 1.222 1.0 9 

0.03576 3.22 3.78 0.18 0.18 0.55 0.91 1.0 0.36 1.222 1.0 10 

0.03576 3.46 3.54 0.06 0.06 0.910.28 1.00.12 1.222 1.0 11 

0.03576 3.58 3.42 0.06 0.06 0.25 0.28 1.0 0.12 1.222 1.0 12 

0.03576 3.70 3.30 0.06 0.06 0.28 0.911.00.12 1.222 1.0 13" 

0.035763.823.180.060.060.910.28 1.00.12 1.222 1.0 14 

0.03576 3.94 3.06 0.06 0.06 0.28 0.28 1.00.12 1.222 1.0 15 

0.03576 4.06 2.94 0.06 0.06 0.28 0.91 1.0 0.12 1.222 1.0 16 

0.03576 4.18 2.82 0.06 0.06 0.910.28 1.00.12 1.222 1.0 17 

0.03576 4.30 2.70 0.06 0.06 0.28 0.28 1.0 0.12 1.222 1.0 18 

0.03576 4.42 2.58 0.06 0.06 0.28 0.91 1.0 0.12 1.222 1.0 19 

0.03576 4.54 2.46 0.06 0.06 0.91 0.28 1.00.12 1.222 1.0 20

E-12
10051921 

10051922 

10051923 

10051924 

10051925 

10051926 

10051927 

10051928 

10051929 

10051930 

10051931 

10051932 

10051933 

10051934 

10051935 

10051936 

10051937 

10051938 

10051939 

10051940 

10052000 

10052100 

10052101 

10052102 

10052201 

10052301 

10052401 

*10052000 

*10052100 

*10052101 

*10052102 

*10052103 

*10052104 

*10052201 

*10052301 

*10052401 

10052501 

10052502 

10052503 

10052601 

10052602 

10052603 

10052701 

10052702 

10052703 

10052900 

10052900 

10052902 

10052903 

10052904 

10052905 

10052906 

10052907 

10052908 

10052909 

10052910 

10052910 

10052912 

10052913 

10052914 

10052915 

10052916 

10052917 

10052918 

10052919 

10052920 

10052921 

10052922 

10052923 

10052924 

10052925 

10052926 

10052927 

10052928 

10052929 

10052930 

10052931 

10052932

0.03576 4.66 2.34 0.06 0.06 0.28 0.28 1.0 0.12 1.222 1.0 21 

0.03576 4.78 2.22 0.06 0.06 0.28 0.91 1.0 0.12 1.222 1.0 22 

0.03576 4.90 2.10 0.06 0.06 0.910.28 1.00.12 1.222 1.0 23 

0.03576 5.02 1.98 0.06 0.06 0.28 0.28 1.0 0.12 1.222 1.0 24 

0.03576 5.14 1.86 0.06 0.06 0.28 0.91 1.00.12 1.222 1.0 25 

0.03576 5.26 1.74 0.06 0.06 0.91 0.28 1.0 0.12 1.222 1.0 26 

0.03576 5.38 1.62 0.06 0.06 0.28 0.28 1.0 0.12 1.222 1.0 27 

0.03576 5.50 1.50 0.06 0.06 0.28 0.91 1.00.12 1.222 1.0 28 

0.03576 5.62 1.38 0.06 0.06 0.91 0.28 1.0 0.12 1.222 1.0 29 

0.03576 5.74 1.26 0.06 0.06 0.28 0.28 1.0 0.12 1.222 1.0 30 

0.03576 5.86 1.14 0.06 0.06 0.28 0.911.0 0.12 1.222 1.0 31 

0.03576 5.98 1.02 0.06 0.06 0.91 0.28 1.0 0.12 1.222 1.032 

0.03576 6.10 0.90 0.06 0.06 0.28 0.28 1.0 0.12 1.222 1.0 33 

0.03576 6.22 0.78 0.06 0.06 0.28 0.911.0 0.12 1.222 1.0 34 

0.03576 6.34 0.66 0.06 0.06 0.91 0.28 1.0 0.12 1.222 1.0 35 

0.03576 6.46 0.54 0.06 0.06 0.28 0.28 1.0 0.12 1.222 1.0 36 

0.03576 6.58"0.42 0.06 0.06 0.28 0.91 1.0 0.12 1.222 1.0 37 

0.03576 6.70 0.30 0.06 0.06 0.91 0.28 1.0 0.12 1.222 1.0 38 

0.03576 6.82 0.18 0.06 0.18 0.28 0.28 1.0 0.12 1.222 1.0 39 

0.03576 6.94 0.06 0.06 0.06 0.28 0.91 1.0 0.12 1.222 1.0 40 

40 5 2 0 0.00275 

01 

1 0.004 1 0.005 

1 0.006 1 0.00675 

14 

1.4 

527.3 5 

40 17 2 00.00275 

01 

1 0.003 1 0.00325 1 0.0035 1 0.00375 

1 0.004 1 0.00425 1 0.0045 1 0.00475 

1 0.005 1 0.00525 1 0.0055 1 0.00575 

1 0.006 1 0.00625 1 0.0065 1 0.00675 

116 

1.16 

527.3 17 

0001 1.92 1 

00014.3210 

00011.4440 

005020000 10000 110 1 1.92 1 

005030000 10000 110 14.32 10 

005120000 10000 110 1 1.4440 

001 0.016167618441 0.0 0.0 1 

001 0.036377142554 0.0 0.0 10 

001 0.012125714185 0.0 0.0 40 

1 

0.01788 0.08 5.92 0.08 0.08 0.55 0.55 1.0 0.16 1.222 1.0 1 

0.01788 0.34 6.66 0.18 0.18 0.55 0.55 1.0 0.36 1.222 1.0 2 

0.01788 0.70 6.30 0.18 0.18 0.55 0.55 1.0 0.36 1.222 1.0 3 

0.01788 1.06 5.94 0.18 0.18 0.55 0.55 1.0 0.36 1.222 1.04 

0.01788 1.42 5.58 0.18 0.18 0.55 0.55 1.0 0.36 1.222 1.0 5 

0.01788 1.78 5.22 0.18 0.18 0.55 0.55 1.0 0.36 1.222 1.0 6 

0.01788 2.14 4.86 0.18 0.18 0.55 0.55 1.0 0.36 1.222 1.0 7 

0.01788 2.504.50 0.18 0.18 0.55 0.55 1.0 0.36 1.222 1.0 8 

0.01788 2.86 4.14 0.18 0.18 0.55 0.55 1.0 0.36 1.222 1.0 9 

0.01788 3.22 3.78 0.18 0.18 0.55 0.91 1.0 0.36 1.222 1.0 10 

0.01788 3.46 3.54 0.06 0.06 0.910.28 1.0 0.12 1.222 1.0 11 

0.01788 3.58 3.42 0.06 0.06 0.25 0.28 1.0 0.12 1.222 1.0 12 

0.01788 3.70 3.30 0.06 0.06 0.28 0.91 1.0 0.12 1.222 1.0 13 

0.01788 3.82 3.18 0.06 0.06 0.91 0.28 1.00.12 1.222 1.0 14 

0.01788 3.94 3.06 0.06 0.06 0.28 0.28 1.0 0.12 1.222 1.0 15 

0.01788 4.06 2.94 0.06 0.06 0.28 0.91 1.0 0.12 1.222 1.0 16 

0.01788 4.18 2.82 0.06 0.06 0.91 0.28 1.0 0.12 1.222 1.0 17 

0.01788 4.30 2.70 0.06 0.06 0.28 0.28 1.0 0.12 1.222 1.0 18 

0.01788 4.42 2.58 0.06 0.06 0.28 0.91 1.0 0.12 1.222 1.0 19 

0.01788 4.54 2.46 0.06 0.06 0.91 0.28 1.0 0.12 1.222 1.0 20 

0.01788 4.66 2.34 0.06 0.06 0.28 0.28 1.0 0.12 1.222 1.0 21 

0.01788 4.78 2.22 0.06 0.06 0.28 0.91 1.00.12 1.222 1.0 22 

0.01788 4.90 2.10 0.06 0.06 0.91 0.28 1.0 0.12 1.222 1.0 23 

0.01788 5.02 1.98 0.06 0.06 0.28 0.28 1.0 0.12 1.222 1.0 24 

0.01788 5.14 1.86 0.06 0.06 0.28 0.91 1.00.12 1.222 1.0 25 

0.01788 5.26 1.74 0.06 0.06 0.910.28 1.00.12 1.222 1.0 26 

0.01788 5.38 1.62 0.06 0.06 0.28 0.28 1.0 0.12 1.222 1.0 27 

0.01788 5.50 1.50 0.06 0.06 0.28 0.91 1.0 0.12 1.222 1.0 28 

0.01788 5.62 1.38 0.06 0.06 0.91 0.28 1.0 0.12 1.222 1.0 29 

0.01788 5.74 1.26 0.06 0.06 0.28 0.28 1.0 0.12 1.222 1.0 30 

0.01788 5.86 1.14 0.06 0.06 0.28 0.91 1.0 0.12 1.222 1.0 31 

0.01788 5.98 1.02 0.06 0.06 0.910.28 1.0 0.12 1.222 1.0 32

8 1.00.121.2221.033 1 1.00.12 1.222 1.034 

8 1.00.121.222 1.035 

8 1.00.12 1.222 1.036 

'11.00.121.222 1.037 

.8 1.00.12 1.2221.038 

;8 1.00.12 1.222 1.0 39 

'11.00.121.222 1.040

10052933 0.01788 6.10 0.90 0.06 0.06 0.28 0.2 

10052934 0.01788 6.22 0.78 0.06 0.06 0.28 0.9 

10052935 0.017886.34 0.66 0.06 0.06 0.91 0.2 

10052936 0.01788 6.46 0.54 0.06 0.06 0.28 0.2 

10052937 0.01788 6.58 0.42 0.06 0.06 0.28 0.9 

10052938 0.017886.700.300.060.06 0.91 0.2 

10052939 0.01788 6.82 0.18 0.06 0.18 0.28 0.2 

10052940 0.01788 6.94 0.06 0.06 0.06 0.28 0.9 

10053000 452200.00 

10053100 0 1 

10053101 1 0.0075 

10053201 11 

10053301 0. I 

10053401 527.45 2 

10053501 0GO 10.578 1 

10053502 00010.16 2 

10053503 00010.36 11 

10053504 00010.12 41 

10053505 0 0 0 1 0.13143 

10053506 00010.09844 

10053507 00010.1 45 

10053601 005010000 10000 110 10.578 1 

10053602 005020000 10000 110 1 0.16 2 

10053603 005030000 10000 110 1 0.36 11 

10053604 005120000 10000 110 10.12 41 

10053605 005420000 10000 110 10.13143 

10053606 005440000 10000 110 1 0.098 44 

10053607 005450000 10000 110 10.1 45 

10053701 00.00.0 0.045 

10053901 0.0 15.0 15.0 0.0 0.0 0.0 0.0 1.0 45 

10054000 453200.04 

10054100 0 1 

10054101 1 0.055 

10054102 1 0.0625 

10054201 3122 

10054301 0.02 

10054401 530.03 

10054501 005010000 10000 110 1 0.578 1 

10054502 005020000 10000 110 10.16 2 

10054503 005030000 10000 110 10.36 11 

10054504 0051200001000011010.12 41 

10054505 005420000 10000 110 10.13143 

10054506 005440000 10000 110 10.098 44 

10054507 005450000 10000 110 10.1 45 

10054601 -12030111 0.578 1 

10054602 -1203011 10.16 2 

10054603 -12 0 301110.36 11 

10054604 -120301110.12 41 

10054605 -1203011 10.13143 

10054606 -1203011 10.09844 

10054607 -1203011 10.1 45 

10054701 0 0.00.00.045 

10054801 0.0 15.0 15.0 0.0 0.0 0.0 0.0 1.045 

* lifting path tube 

10071000 42200.0365 

10071100 01 

10071101 10.0445 

10071201 2 1 

10071301 0.0 1 

10071401 550.02 

10071501 007010000 00000 11 0.38 1 

10071502 007020000 00000 1 10.35 2 

10071503 007030000 10000 11 0.79753 

10071504 007040000 10000 1 10.7954 

10071601 -1203011 10.38 1 

10071602 -1203011 10.35 2 

10071603 -1203011 10.79753 

10071604 -1203011 10.7954 

10071701 00.00.00.04 

10071801 0.0 15.0 15.00.00.00.00.0 1.04 

* lifting path tube 

10072000 7 2200.051 

10072100 01 

10072101 10.057 

10072201 2 1

E-13
10072301 

10072401 

10072501 

10072502 

10072503 

10072504 

10072505 

10072601 

10072602 

10072603 

10072604 

10072605 

10072701 

10072801

0.0 1 

550.02 

007050000 10000 1 11.635 3 

007080000 0 1 1 1.07 4 

007090000 0 11 0.68 5 

007100000 0 110.1 6 

00711000001 10.247 

-1203011 1 1.635 3 

-1203011 1 1.07 4 

-1203011 10.68 5 

-1203011 10.1 6 

-1203011 10.24 7 

0 0.0 0.0 0.07 

0.0 15.0 15.0 0.0 0.0 0.0 0.0 LO 

7

* swc tube 

10091000 20 2 2 0 0.0325 

10091100 01 

10091101 10.0375 

10091201 2 1 

10091301 0.0 1 

10091401 550.02 

10091501 009010000 10000 11 0.75 2 

10091502 009030000 10000 11 0.6 3 

10091503 009050000 10000 11 1.375 5 

10091504 009060000 10000 11 0.8 6 

10091505 009070000 10000 1 11.3 7 

10091506 00908000000000 111.4 8 

10091507 009090000 00000 110.8 9 

10091508 009100000000001 12.15 10 

10091509 009150000 00000 1 12.26 15 

10091510 009170000 00000 1 11.7175 17 

10091511 009180000 00000 1 12.3 18 

10091512 009190000 00000 1 10.7 19 

10091513 00920000000000 110.5 20 

10091601 -1203011 10.75 2 

10091602 -1203011 10.6 3 

10091603 -1203011 1 1.375 5 

10091604 -1203011 10.8 6 

10091605 -1203011 11.3 7 

10091606 -1203011 11.4 8 

10091607 -1203011 10.8 9 

10091608 -1203011 12.15 10 

10091609 -1203011 12.26 15 

10091610 -1203011 1 1.7175 17 

10091611 -120301112.3 18 

10091612 -1203011 10.7 19 

10091613 -1203011 10.5 20 

10091701 0 0.0 0.0 0.0 20 

10091801 0.0 15.0 15.00.00.00.00.0 1.020

* upper header tube 

10111000 62200.1475 

10111100 01 

10111101 10.1635 

10111201 21 

10111301 0.01 

10111401 536.02 

10111501 010010000 000 

10111502 011010000100 

10111503 011050000000 

10111601 -1203011 10.' 

10111602 -1203011 10." 

10111603 -12 03011 10.0 

10111701 00.0 0.0 0.006 

10111801 0.0 15.0 15.00.

10141506 

10141507 

10141508 

10141601 

10141602 

10141603 

10141604 

10141605 

10141606 

10141607 

10141608 

10141701 

10141801

01406000010000 1 11.0 6 

014070000 10000 1 11.5 7 

014080000 10000 11 0.5 8 

-1203011 1 0.9 1 

-1203011 1 1.0 2 

-12030111 1.3 3 

-12030111 1.5 4 

-12030111 0.8 5 

-1203011 1 1.0 6 

-12030111 1.5 7 

-12030111 0.5 8 

0 0.00.00.08 

0.0 15.0 15.0 0.0 0.0 0.0 0.0 1.08

* separator tube 

10201000 82200.091 

10201100 01 

10201101 10.111 

10201201 21 

10201301 0.01 

10201401 536.02 

10201501 020010000 10000 1 10.52 

10201502 020020000 10000 110.7 3 

10201503 020020000 10000 11 0.5 8 

10201601 -12 0 3011 10.5 2 

10201602 -12 0 3011 10.7 3 

10201603 -12 0 3011 10.5 8 

10201701 00.0 0.0 0.08 

10201801 0.0 15.0 15.00.00.00.00.0 1.08 

* downcm22 pipe 

10221000 142200.051 

10221100 01 

10221101 10.057 

10221201 2 1 

10221301 0.01 

10221401 536.02 

10221501 022010000 10000 1 1 1.15 2 

10221502 022030000 10000 1 1 1.05 4 

10221503 022050000 10000 1 1 1.425 6 

10221504 022070000 10000 1 1 1.2 10 

10221505 022110000 10000 1 11.325 12 

10221506 022130000 10000 1 1 1.3 13 

10221507 022140000 10000 1 1 1.275 14 

10221601 -1203011 11.15 2 

10221602 -1203011 11.05 4 

10221603 -12030111 1.425 6 

10221604 -12030111 1.2 10 

10221605 -12030111 1.32512 

10221606 -1203011 1 1.3 13 

10221607 -1203011 1 1.27514 

10221701 0 0.0 0.00.0 14 

10221801 0.0 15.0 15.0 0.0 0.0 0.0 0.0 1.0 14 

* steam pipe 

10301000 122200.051 

10301100 01 

10301101 10.057 

10301201 2 1 

10301301 0.0 1 

10301401 550.02 

10301501 030010000 10000 11 0.6 1 

10301502 030020000 10000 11 0.8 2 

10301503 030030000 10000 11 0.7 3 

10301504 030040000 10000 11 0.95 4 

10301505 030050000 10000 1 11.4756 

10301506 030070000 10000 1 11.4 7 

10301507 030080000 10000 1 1 1.7 8 

10301508 030090000 10000 1 10.75 9 

10301509 030100000 10000 1 1 0.65 10 

10301510 030110000 10000 1 10.7 12 

10301601 -1203011 10.6 1 

10301602 -1203011 10.8 2 

10301603 -1203011 10.7 3 

10301604 -1203011 10.954 

10301605 -1203011 11.4756 

10301606 -1203011 11.4 7 

10301607 -1203011 11.7 8 

10301608 -1203011 10.75 

9

10 10.7 1 

001 10.7 5 

001 10.9 6 

71 

75 

906 

0 0.0 0.0 0.0 1.0 

6

* swpline pipe 

10141000 82200.05 

10141100 01 

10141101 10.06 

10141201 2 1 

10141301 0.0 1 

10141401 550.02 

10141501 014010000000001 10.9 1 

10141502 014020000 10000 1 1 1.0 2 

10141503 014030000 10000 1 1 1.3 3 

10141504 014040000 10000 1 11.5 4 

10141505 014050000 10000 11 0.8 

5

E-14
10301609 -1203011 10.65 10 

10301610 -1203011 10.7 12 

10301701 0 0.0 0.0 0.0 12 

10301801 0.0 15.0 15.0 0.0 0.0 0.0 0.0 1.0 12 

* downcm34 pipe 

10341000 152200.051 

10341100 01 

10341101 10.057 

10341201 2 1 

10341301 0.0 1 

10341401 527.452 

10341501 034010000 10000 11 0.85 1 

10341502 034020000 10000 11 1.7 2 

10341503 034030000 10000 1 I 0.85 3 

10341504 034040000 10000 1 12.0 4 

10341505 034050000 10000 1 1 1.7 5 

10341506 034060000 10000 1 1 1.843 8 

10341507 034090000 10000 1 1 2.4 9 

10341508 034100000 10000 1 3 1.85 11 

10341509 034120000 10000 1 1 1.586 12 

10341510 034130000 10000 1 1 1.435 13 

10341511 034140000 10000 1 1 1.42 15 

10341601 -120301110.85 1 

10341602 -1203011 1 1.7 2 

10341603 -1203011 10.85 3 

10341604 -1203011 12.0 4 

10341605 -1203011 11.7 5 

10341606 -1203011 11.8438 

10341607 -120301112.4 9 

10341608 -1203011 11.85 11 

10341609 -1203011 11.58612 

10341610 -1203011 11.435 13 

10341611 -1203011 11.42 15 

10341701 00.00.00.015 

10341801 0.0 15.0 15.0 0.0 0.0 0.0 0.0 1.0 15 

* downcm52 pipe 

10521000 14 2 2 0 0.0715 

10521100 01 

10521101 10.0795 

10521201 2 1 

10521301 0.01 

10521401 536.02 

10521501 052010000 10000 1 1 1.663 3 

10521502 052040000 10000 1 12.2 4 

10521503 052050000 10000 1 1 1.9 5 

10521504 052060000 10000 1 3 1.6 6 

10521505 052070000 10000 1 1 1.5 8 

10521506 052090000 10000 1 1 1.9 9 

10521507 052100000 10000 11 2.45 10 

10521508 052110000 10000 1 11.5 11 

10521509 052120000 10000 1 11.516 12 

10521510 052130000 10000 1 1 1.45 14 

10521601 -1203011 1 1.663 3 

10521602 -1203011 12.2 4 

10521603 -1203011 11.9 5 

10521604 -1203011 1 1.6 6 

10521605 -1203011 1 1.5 8 

10521606 -1203011 11.9 9 

10521607 -1203011 1 2.45 10 

10521608 -1203011 1 1.5 11 

10521609 -1203011 11.51612 

10521610 -1203011 1 1.45 14 

10521701 00.00.00.0 14 

10521801 0.0 15.0 15.0 0.0 0.0 0.0 0.0 1.0 14 * 

* downcm62 pipe 

10621000 82200.0715 

10621100 01 

10621101 10.0795 

10621201 2 1 

10621301 0.01 

10621401 536.02 

10621501 062010000 10000 1 1 1.72 3 

10621502 062040000 10000 1 1 1.375 4 

10621503 062050000 10000 1 1 1.35 5 

10621504 062060000 10000 1 1 1.325 6 

10621505 062070000 10000 1 1 1.2 7

10621506 062080000 10000 1 11.2 8 

10621601 -1203011 1 1.72 3 

10621602 -1203011 1 1.375 4 

10621603 -1203011 1 1.35 5 

10621604 -1203011 1 1.325 6 

10621605 -1203011 1 1.2 7 

10621606 -1203011 1 1.2 8 

10621701 00.00.00.08 

10621801 0.0 15.0 15.0 0.0 0.0 0.0 0.0 1.08 

* bypass pipe 

11061000 242200.051 

11061100 01 

11061101 1 0.057 

11061201 21 

11061301 0.01 

11061401 527.452 

11061501 106010000 10000 1 11.0 2 

11061502 106030000 10000 1 11.5113 

11061503 106040000 10000 1 11.3 4 

11061504 106050000 10000 1 1.1374456 

11061505 106070000 10000 1 1 1.55 7 

11061506 106080000 100001 1 1.1425 11 

11061507 106120000 10000 1 1 1.4 13 

11061508 106140000 10000 1 1 1.7 14 

11061509 1061500001 0000 1 1 1.3 15 

11061510 106160000 10000 1 1 1.4 17 

11061511 106180000 10000 11 1.3842 22 

11061512 106230000 10000 1 10.6 24 

11061601 -1203011 11.0 2 

11061602 -1203011 11.5113 

11061603 -12030111 1.3 4 

11061604 -1203011 1 1.1374456 

11061605 -1203011 1 1.55 7 

11061606 -1203011 11.1425 11 

11061607 -1203011 1 1.4 13 

11061608 -1203011 1 1.7 14 

11061609 -1203011 1 1.3 15 

11061610 -1203011 11.4 17 

11061611 -1203011 1 1.3842 22 

11061612 -1203011 10.6 24 

11061701 00.00.00.024 

11061801 0.0 15.0 15.0 0.0 0.0 0.0 0.0 1.024 * ****   ** * ** ************* ***** ***   ** * ********* * 

* GENERAL TABLES 

* MATEREAL 

20100100 s-steel 

20100200 s-steel 

20100300 tbl/fcm 1 1 

20100301 1.15 

20100351 2.465+6 

* HEAT SOURCE 

20200100 power01. 1000.0 

20200101 0.00 0000.0 

20200102 10.00 2486.0 

* HEAT LOSS 

* S*** ** ** *5 ***** ********* *5*5****** *5****** *5**5***** 

20200200 htrnrate 0 1.0 1.0 

20200201 0.0 2282.12 

**heat 

20200300 temp 0 

20200301 0.00 560.0 

20201100 htc-t 0 

20201101 0.00 10.0 

20201200 temp 0 

20201201 0.00 295.0 

.*end of data set 

0000100 restart ransnt 

*0000101 inp-chk

E-15
0000102si si 

0000103 198474 cmpress 

0000202 1350. 1.0-6 0.01 15003 500 40000 4000000 

0000203 1400. 1.0-6 0.01 15003 100 40000 4000000 

*0000204 1460. 1.0-6 0.01 15003 10 40000 4000000 

*0000205 1600. 1.0-6 0.01 15003 500 40000 4000000 

1000000 tdvlOO delete 

1010000 outleg delete , 

.end data set 

0000100 restart transnt 

*0000101 inp-chk 

0000102 si si 

*0000103 198457 cmpress 

0000103 278474 *1400 s *0000103297835 *1500s 

*0000202 1350. 1.0-6 0.01 15003 500 40000 4000000 

0000203 1400. 1.0-6 0.01 15003 100 10000 10000 

0000204 1800. 1.0-6 0.01 15003 10 10000 10000 *0000205 1500. 1.0-6 0.01 15003 500 40000 4000000 

*1!000000 tdvlO0 delete 

*1010000 outleg delete 

* isolating control valve 2r 

0020000 valv2r valve 

*crdno from to area floss rloss efvcahs 

0020101 001010000 003000000 3.3183-3 775.0 775.0 0001100 

0020201 1 3.9 0.0 0.0 

0020300 mtrvlv 

* open close rate inil table 

0020301 702 602 0.25 1.0 0 

412 time 0 ge null 0 1408.7 n * close 

512 time 0 ge null 0 1416.0 n * stop 

602 412 and -512 n *close 

403 time 0 ge null 0 1420.00 n * open 

503 time 0 ge null 0 1420.17 n * stop 

702 403 and -503 n * open 

.end data set

E-16
NRC FORM 336 U.S. NUCLEAR REGULATORY COMMISSION 1. REPORT NUMBER 

2-89 (Assigned by NRC, Add VoL, Supp., Rev., 

RC-M 1102, mId Addedum Numbers Nf any.) 

3201, 302 BIBLIOGRAPHIC DATA SHEET 

(See instrucions on a*e evewme) 

2. TITLE AND SUBTITLE NUREG/IA-0202 

Analyses of KS Test Data on the Heated Rod Bundle Temperature Behavior in RBMK-1 500 

Core Model Under Stop and Recovery Flow Using RELAP5/MOD3.2 and RELAPS/MOD3.2.2 3. DATE REPORT PUBUSHED 

GAMMA MONTH YEAR 

April 2001 

4. FIN OR GRANT NUMBER 

5. AUTHOR(S) 6. TYPE OF REPORT 

V.A. Vinogradov, A.Y. Balykin Technical 

7. PERIOD COVERED (Ictusive Dates) 

8. PERFORMING ORGANIZATION - NAME AND ADDRESS (if NRC, provide Division, Ofice or Region, U.S. Nudear Regulatory Commission, and maifing addiewss if conrctor, 

provide name and maifing addess.) 

Nuclear Reactor Institute, Russian Research Center 

Kurchatov Institute 

Kurchatov Square 1 

123182, Moscow Russia

9. SPONSORING ORGANIZATION - NAME AND ADDRESS (If NRC, type 'Same asabove'; if oontrctor, provide NRC Division, Ofice or Region, U.S. Nudear R0egulatory .omsion 

and mailig address)

Division of Systems Analysis and Regulatory Effectiveness 

Office of Nuclear Regulatory Research 

U.S. Nuclear Regulatory Commission 

Washington, DC 20555-0001 

10. SUPPLEMENTARY NOTES 

11. ABSTRACT (200 words orless) 

This report has been prepared as a part of the Agreement on Research Participation and Technical Exchange under the 

International Code Application and Maintenance Program. KS expenmental data on the behavior of the heated rod bundle 

temperature in the RBMK-1 500 core model under stop and recovery flow conditions were simulated with RELAP5M•OD3.2 and 

RELAP5/MOD3.2.2 GAMMA to assess the codes suitability. Especially calculations were performed to estimate differences in 

the code version predictions for processes/phenomena, which could occur under specific conditions of RBMK type reactor 

during LOCA with MCP's pressure header rupture and subsequent ECCS water injection. This problem addresses 

phenomena of high importance to RBMK-1500 safety including water discharge, critical heat flux, post dryout heat transfer, 

reflood and propagation of rewetting front in the fuel channel during an accident. The tests has been carded out at KS 

semi-integral test facility (Russian Research Center Kurchatov Institute) represented RBMK primary circuit. The main purpose 

of the experiment was investigation of temperature conditions in the fuel assembly under high power value, inlet flow rate 

being decreased drastically up to complete stop of the flow followed by pressure header rupture. A subsequent flow rate 

resumption was also assumed, the fuel assembly power high level being unchanged. First, a study of the effect of the 

hydraulic nodalization to the code calculations was performed using different number of hydraulic volumes for the fuel channel 

model. After the choice of proper nodalization and maximum user-specified time step, base case calculations were done for 

the test. Sensitivity studies were carried out to investigate the effects of modeling on the behavior of the rod simulator 

temperatures along the height of the fuel assembly model.

12. KEY WORDS/DESCRIPTORS (List words orphrases tat mi1 assist reseemiersin tosbag Me report.) 13. AVAILABILITY STATEMENT 

RELAP5 unlimited 

RBMK 14. SECURn'Y CLASSFCATION 

LOCA (This P ) 

unclassified 

(This Report) 

unclassified 

15. NUMBER OF PAGES 

16. PRICE

NRC FORM 335 (2-89)
Federal Recycling Program
NUREG/IA-0202 ANALYSES OF KS TEST DATA ON THE HEATED ROD BUNDLE TEMPERATURE BEHAVIOR IN RBMK-1500 

CORE MODEL UNDER STOP AND RECOVERY FLOW USING RELAPS/MOD3.2 AND RELAP5/MOD3.2.2 GAMMA

UNITED STATES 

NUCLEAR REGULATORY COMMISSION 

WASHINGTON, DC 20555-0001 

OFFICIAL BUSINESS 

PENALTY FOR PRIVATE USE, $300

APRIL 2001