Integral Experiments Data, Databases, Benchmarks and Safety Joint Projects
CSNI2200 PSB-VVER.
last modified: 05-JAN-2009 | catalog | new | search |

CSNI2200 PSB-VVER.

PSB-VVER, Computer code validation for transient analysis of VVER and RBMK reactors project

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1. NAME

PSB-VVER.

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2. COMPUTERS

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Program name Package id Status Status date
PSB-VVER CSNI2200/01 Arrived 05-JAN-2009

Machines used:

Package ID Orig. computer Test computer
CSNI2200/01 Many Computers
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3. DESCRIPTION

The NEA PSB-VVER project provided unique and useful experimental data for code validation using the PSB-VVER test facility. The PSB-VVER facility is a large-scale thermal-hydraulics testing facility operated by the Electrogorsk Research and Engineering Centre (EREC) in Russia which represents the scaled-down layout of the Russian-designed pressurised water reactor, namely, VVER-1000. The PSB-VVER Project was intended to provide the experimental data needed to allow full validation of the computer codes used in the thermal-hydraulic analysis of VVER-1000 reactors*.

 

VVER-1000 reactors have design characteristics that are similar to western-designed pressurised water reactors (PWRs). There are however important design differences which necessitate specific experimental facilities and data to ensure that the computer codes are validated and that the results of the thermal-hydraulic analyses are of acceptable quality for this type of reactor.

 

Earlier NEA work established a code validation matrix for both LWRs and VVERs. This matrix is essentially a set of phenomena and experimental data that is used to validate thermal-hydraulic computer codes. This led to the general conclusion that the VVER-1000 matrix was not complete. Consequently, it was decided to develop the NEA PSB-VVER project to obtain the required experimental data not covered by the matrix.

 

The project provided unique experimental data needed for the validation of thermal-hydraulic codes and to support refinements to the safety assessment tools for VVER-1000 reactors. The PSB-VVER experiments represent a relevant extension of the existing code validation database. The generated data is of relevance to the VVER-1000 systems, but could potentially also be of interest to other types of pressurised water reactors.

 

Five experiments were executed, dealing with loss of coolant scenarios (small, intermediate, and large break loss of coolant accidents), a primary-to-secondary leak, and a parametric study (natural circulation test) aimed at characterising the VVER system at reduced mass inventory conditions.The scope of the project addressed the following areas:

  • scaling effects

  • natural circulation

  • small cold leg break loss-of-coolant accidents

  • primary to secondary leak

  • 100% double-ended cold leg break

 

Extensive pre- and post-test analyses accompanied the programme throughout the entire experimental series.

 

A comparative analysis regarding the large break loss of coolant accident experiment can be found at Validation of Advanced Computer Codes for VVER Technology: LB-LOCA Transient in PSB-VVER Facility.

 

Related research on thermalhydraulics projects can be found at Integral Test Facilities and Thermal-Hydraulic System Codes in Nuclear Safety Analysis.

 

Participating countries: Czechia, Finland, France, Germany, Italy, Russia and United States.

 

Project period: February 2003 - December 2008

 

The distribution of this package is restricted and subject to prior approval.

 

For more information see Nuclear Energy Agency (NEA) - PSB-VVER Project

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9. STATUS
Package ID Status date Status
CSNI2200/01 05-JAN-2009 Masterfiled restricted
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10. REFERENCES
CSNI2200/01, included references:
- O.I. Melikhov, V.I. Melikhov, I.V. Parfenov:
PSB-VVER tests priority for the OECD PSB-VVER Project (PSB-VVER REPORT, PSB-01)
- O.I. Melikhov, I.V. Elkin, I.A. Lipatov, G.I. Dremin and S.A. Galchanskaya:
Guidelines for Performance of PSB-VVER Tests (PSB-VVER REPORT, PSB-02)
- O.I. Melikhov  et al.:
Report about PSB-VVER Description (including Measurement System)(PSB-VVER
REPORT, PSB-03)
- Ilya.V. Elkin, George I. Dremin, Igor A. Lipatov, S.vetlana A. Galchanskaya:
Report about PSB-VVER Heat Losses (PSB-VVER REPORT, PSB-04)
- I.V. Elkin, I.A. Lipatov, A.I. Antonova, G.I. Dremin, M.A. Berezutskaya:
Report about PSB-VVER Hydraulic Losses (PSB-VVER REPORT, PSB-05)
- O.I. Melikhov et al.:
Pre-test Experiment Proposal Report (Test 1) (PSB-VVER REPORT PSB-06)
- O.I. Melikhov et al.:
Post-test Quick Look Experimental Data (Test 1)(PSB-VVER REPORT, PSB-07)
- O.I. Melikhov et al.:
Post-test Full Experimental Data Report (Test 1) (PSB-VVER REPORT, PSB-08)
- O.I. Melikhov et al.:
Standard Problem Definition Report (Test 1) (PSB-VVER REPORT PSB-09)
- O. V. Gavritenkova, I. V. Parfenov, O.I. Melikhov, V.I. Melikhov:
Standard Problem RELAP5/MOD3.2 Analysis Report (Test 1) (PSB-VVER REPORT PSB-12)
- O. V. Gavritenkova et al.:
Comparative Assessment Report (Test 1) (PSB-VVER REPORT, PSB-13)
- A.G.Kraev:
Code Maintenance Report (Test 1) (PSB-VVER REPORT, PSB-14)
- O.I.Melikhov et al.:
Pre-test Experiment Proposal Report (Test 2) (PSB-VVER REPORT PSB-10)
- O.I.Melikhov et al.:
Post-test Quick Look Report (Test 2) (PSB-VVER REPORT PSB-11)
- O.I.Melikhov et al.:
Post-test Full Experimental Data Report (Test 2) (PSB-VVER REPORT, PSB-15)
- O.I.Melikhov:
Pre-test Experiment Proposal Report (Test 3) (PSB-VVER REPORT, PSB-16)
- O.I. Melikhov, I.V. Elkin, I.A. Lipatov, G.I. Dremin, S.M. Nikonov, S.A.
Galchanskaya, A.V. Kapustin, A.A. Rovnov, V.I. Gudkov, A.I. Antonova, A.F.
Chalych:
Post-test Quick Look Report (Test 3) (PSB-VVER REPORT, PSB-17)
- O.I. Melikhov, I.V. Elkin, I.A. Lipatov, G.I. Dremin, S.M. Nikonov, A.V.
Kapustin, A.A. Rovnov, V.I. Gudkov, A.I. Antonova:
Post-test Full Experimental Data Report (Test 3) (PSB-VVER REPORT, PSB-18)
- Ilya V. Elkin, Igor A. Lipatov, Alexandra I. Antonova, Sergey M. Nikonov,
George I. Dremin, Andrey V. Kapustin:
Single-phase Performance Characteristics of the PSB-VVER Pump (PSB-VVER REPORT,
PSB-19)
- I.V.Elkin, A.I.Suslov, O.I.Melikhov:
Pre-test Experimental Proposal Report (Test 4) (PSB-VVER REPORT, PSB-20)
- O.I. Melikhov et al.:
Standard Problem Definition Report (Test 3) (PSB-VVER REPORT, PSB-21)
- O.I. Melikhov et al.:
Standard Problem Final Analysis Report (Test 3) (PSB-VVER REPORT, PSB-22)
- O.I. Melikhov et al.:
Post-test Final Analysis Report (Test 2) (PSB-VVER REPORT, PSB-23)
- O.I. Melikhov et al.:
Analytical Exercisse Specification Document
Test 4: Primary to Secondary Leak (PSB-VVER REPORT, PSB-24)
- I.V. Elkin et al.:
Post-test Quick Look Report Test 4 (PSB-VVER REPORT, PSB-25)
- I.V. Elkin et al.:
Experimental Data Report Test 4 (PSB-VVER REPORT, PSB-26)
- O.I. Melikhov, I.V. Elkin, M.P. Gashenko, I.A. Lipatov, G.I. Dremin, A.V.
Kapustin, S.M. Nikonov, A.A. Rovnov, A.V. Basov, V.I. Gudkov, A.I. Antonova:
"Preliminary AE Comparison Report" (Test 4) - July 2005, PSB-27
- O.I. Melikhov, I.V. Elkin, I.A. Lipatov, A.V. Kapustin, G.I. Dremin, S.M.
Nikonov, A.A. Rovnov, A.V. Basov, A.I. Antonova:
"Proposal Report - Test 5: Large Cold Leg Break" (Test 5) - Rev3, 28 Feb. 2007,
PSB-28
- O.I. Melikhov, I.V. Elkin, I.A. Lipatov, M.P. Gashenko, A.V. Kapustin:
"Final AE Comparison Report" (Test 4) - Final, 4 Feb. 2008, PSB-29
- O.I. Melikhov, I.V. Elkin, S.M. Nikonov, A.A. Rovnov:
"Test 5a: Actual Initial and Boundary Conditions" - 14 Feb. 2008, PSB-30
- I.V. Elkin, S.M. Nikonov, A.V. Basov:
"Experimental Data Report - Test 5a" 26 March 2008, PSB-31
- O.I. Melikhov, I.V. Elkin, S.M. Nikonov, A.V. Basov, A.V. Kapustin:
"Final Report - OECD PSB-VVER Project (Version 4)" 31 October 2008, PSB-32
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. NAME AND ESTABLISHMENT OF AUTHORS

Electrogorsk Research and Engineering Centre (EREC)

Moscow region 142530

Russia

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16. MATERIAL AVAILABLE
CSNI2200/01
Reports and data for tests 1, 2, 3, 4 and 5
Reports and data for tests 1, 2, 3 and 4
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: VVER type reactor, matrix.