ML19066A174

NUREG/IA-0502, International Agreement Report - Post-Test Analysis of Cold Leg Small Break 4.1% at PSB-VVER Facility Using Trace V5.0

ML19066A174
Person / Time
Issue date:	03/31/2019
From:	Heralecky P, Kirk Tien Office of Nuclear Regulatory Research, TES, Ltd
To:
Meyd, Donald
References
NUREG/IA-0502
Download: ML19066A174 (89)

Text

UREG/IA-0502 Division of Systems Analysis Office of Nuclear Regul atory Rese arch U.S. Nuclear Regulatory Commiss ion

Manuscript Completed:

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NUREG/IA-0502 Division of Systems Analysis Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commiss ion Washington, DC 20555-0001 Manuscript Completed:

Date PublishedPublished by U.S. Nuclear Regulatory Commiss ion

ABSTRACT

TABLE OF CONTENTS ABSTRACT ................................

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iii LIST OF FIGURES

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........ vii LIST OF TABLES

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ix EXECUTIVE

SUMMARY

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xi ACKNOWLEDGMENT S ................................

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xiii ABBREVIATIONS

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xv 1 INTRODUCTION

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.... 1-1 2 FACILITY AND TEST DESCRIPTIONS

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. 2-1

3 THE TRACE V5.0 CODE

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3-1 4 INPUT DECK DESCRIPTION

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4-1 5 RESULTS.... ................................

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5-1

6 RUN STATISTICS

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.. 6-1 7 CONCLUSIONS

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..... 7-1 8 REFERENCES

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....... 8-1APPENDIX A:

INPUT DECK NODALISATION SCHEMES

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...... A-1 APPENDIX B: APPENDIX B THERMAL-HYDRALIC DIAGRAM ANDMEASUREMENT LOCALISATION AT PSB

-VVER FACILITY

......... B-1 APPENDIX C:

COMPLETE SET OF COMPARISON PLOTS FOR TRACE CALCULATION

................................

................................

.................

C-1

LIST OF FIGURES

LIST OF TABLES

EXECUTIVE

SUMMARY

ACKNOWLEDGMENT S

AB BREVIATIONS AND ACRONYMS

1 INTRODUCTION

2 FACILITY AND TEST DESCRIPTIONS PSB-VVER Facility

Figure 1 General View of PSB

-VVER Facility

Table 1 Main Operational Characteristics of PSB

-VVER Comparing to VVER

-1000 Facility onfigurationTable 2 Test Facility Configuration in CL-4.1-03 Test Equipment Status Initial Conditions Table 3 Measured Initial Condition for CL-4.1-0 3 Te st Boundary Conditions (Test Scenario) Table 4 Main Events During CL-4.1-03 Test Event Time [s]

Table 5 Time Dependence of Dimensionless Core Power

3 THE TRACE V5.0 CODE The TRACE V5.0 Co de Assessment

VVER Typical Features Related to TRACE V5.0 Code Assessment 4 INPUT DECK DESCRIPTION The TRACE Input Deck

TRACE Component Notes Table 6 TRACE Components Statistic Table 7 List of the Main Systems and Components of PSB-VVER TRACE Input Deck PSB system Input deck Used TRACE components

5 RESULTS Steady-State Calculation Table 8 Initial Conditions (TRACE Calculation vs. Experiment Comparison)

T ransient Calculation Time Course of the Transient

Comparison of TRACE Prediction to Reference Data Table 9 Chronology of Main Events (TRACE Calculation vs Experiment Comparison)

Sensitivity Studies Performed

Quantitative Assessment of the Calculations Table 10 ACAP Metrics Settings kkTable 11 Acceptability Criterions

st

6 RUN STATISTICS Table 13 Run Statistics

7 CONCLUSIONS 0.797 very good prediction 0.8 02 very good prediction 0.684 good prediction 0.674 good prediction 0.804 very good prediction 0.807 very good prediction 0.686 good prediction 0.681 good prediction

8 REFERENCES

INPUT DECK NODALISATION SCHEMES Figure -1 TRACE Nodalization Scheme of Primary Circuit of PSB

-VVER Facility Figure -2 TRACE Nodalization Scheme of Secondary Circuit of PSB

-VVER Facility

Figure B-1 PSB-VVER Thermal-Hydraulic Diagram Figure B-2 PSB-VVER Reactor Model Measurements Figure B-3 PSB-VVER Loop 1 and SG-1 Model Measurement COMPLETE SET OF COMPARISON PLOTS FOR TRACE CALCULATION Figure C-1 Primary Pressure Figure C-2 Fuel Cladding Temperature (Top of the Core)

Figure C-3 Pressurizer Level Figure C-4 LPIS Flow (Boundary Condition)

Figure C-5 Accumulators Levels Figure C-6 Accumulators Pressure s

Figure C-7 Fuel Rod Simulator Power (Boundary Condition)

Figure C-8 Core By-pass Power (Boundary Condition)

Figure C-9 Secondary Side Pressures

Figure C-1 0 Steam Generators Levels Figure C-11 Loop 1 Temperatures

Figure C-12 Loop 2 Temperatures

Figure C-13 Loop 3 Temperatures

Figure C-14 Loop 4 Temperatures

Figure C-20 Loop 3 Pressure Differences 2

Figu re C-26 Pressure Differences DP13-DP16 (Upper Pa rt of Upper Plenum)

Figure C-28 Break Flow Figure C-29 Reactor Collapsed Level

Post-Test Analysis of Cold Leg Small Break 4.1% at PSB-VVER Facility using TRACE V5.0 NUREG/IA-0502 Petr Heralecky TES Ltd. Prazska 597 67401 Trebic, Czech Republic Division of Systems Analysis Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 K.Tien, NRC Project ManagerThe U.S. NRC best estimate thermo-hydraulic computer code TRACE V5.0 has been assessed against the "4.1 % cold leg break (CL-4.1-03)" experiment at the large-scale test facility PSB-VVER. The PSB-VVER facility is a 1:300 volume-power scaled model of VVER-1000 NPP located in Electrogorsk, Russia. An extensive TRACE i nput deck of PSB-VVER facility was developed. The model includes all important components of the PSB-VVER facility: reactor, 4 separated loops,pressurizer, HPIS and LPIS ECCS, several break units, main circulation pumps, steam generators, and important partsof secondary circuit. The TRACE (TRAC/RELAP Advanced Computational Engine) is the latest in a series of advanced,best-estimate reactor systems codes developed by the U.S. Nuclear Regulatory Commission in frame of CAMP (CodeApplication and Maintenance Program). The TRACE code is a component-oriented reactor systems analysis codesdesigned to analyze light water reactor transients up to the point of significant fuel damage. The original validation of the TRACE code was mainly based on experiments performed on experimental facilities of typical PWR design. There aresome different features of VVER design comparing to PWR. Therefore the validation of the thermo-hydraulic codes for VVER types of reactors is often required by national regulators. The presented analysis is the latest in series of TRACEand RELAP5 assessment calculations evaluated at the company TES. The purpose of performed analyses is to extend the validation of the TRACE code focus ed on VVER type of NPPs and to support applicability of the TRACE code in theCzech Republic. CAMP (Code Applications and Maintenance Program) SNAP (Symbolic Nuclear Analysis Program)

Research Centre ez, TSO PSB-VVER test facility OECD PSB project Electrogorsk Research and Engineering Institute (EREC) Russian Pressurized Water Type Reactor (VVER)

OECD/NEA/CSNI/WGAMA PSB Project.

201 Technical

NUREG/IA-0502 Post-Test Analysi s of Cold Leg Smal l Brea k 4.1% at PSB-VVER Facility using TRACE V5.0

201