Expert Group on Reactor Stability and LWR Transient Benchmarks

Scope	Objectives	Keywords
List of activities	Related conferences and meetings	Links

Scope

The Expert Group deals with modelling issues in the field of 3-D coupled neutronics / thermal-hydraulics transients for nuclear cores and coupling of core phenomena and system dynamics (PWR, BWR, VVER).
The transients considered include:

Rod Ejection (PWR);
Uncontrolled Withdrawal of Control Rods (PWR);
Main Steam-line Breaks (PWR);
BWR Stability, time series and frequency analysis;
Cold water injection and core pressurisation (BWR);
Turbine Trips (BWR) benchmark;
VVER-1000 Coolant Transient Benchmark (V1000-CT);
BWR Full-size Fine-mesh Bundle Test (BFBT).
Uncertainty Analysis in Modelling (UAM) - Coupled Multi-physics and Multi-scale LWR analysis
Critical Issues in Nuclear Reactor Technology (CRISSUE-S)

Objectives

The objectives of the NSC in the field of coupled neutronics/thermal-hydraulics computing are to advance scientific knowledge needed for the development of advanced modelling techniques for new nuclear technologies and concepts, as well as for current nuclear applications. This includes:

driving of recent development of coupled 3-D neutronics / T-H codes;
validation and benchmarking of their performance through comparison with experiments;
verifying the correctness of methods and computer codes, building confidence in areas where research is very expensive or lacking;
determination of model uncertainties;
promotion of their use in production runs and safety analysis.

Keywords

Reactor Stability, Transient, Coupled Neutronics/Thermal-hydraulics, Coupeld Core/Plant 3D Benchmarks

List of activities

Validation of coupled thermal-hydraulic and neutronics codes in international co-operation by
K. Ivanov, E. Sartori, E. Royer, S. Langenbuch, K. Velkov, Eurosafe 2005 Conference

Benchmarks

Forsmark 1 & 2 BWR Stability Benchmark

nsc-doc99-9.pdf (153 Kbyte)

PWR Main Steam-Line Break Benchmark (PWR-MSLB)

Final Specification ( 740 Kbyte )
Second Workshop ( 41 Kbyte )
Third Workshop ( 45 Kbyte )
Fourth Workshop ( 64 Kbyte )

BWR Turbine Trip Transients Benchmark (BWR-TT)
VVER-1000 Coolant Transient Benchmark (V1000-CT)
BWR Full-size Fine-mesh Bundle tests Benchmark (BFBT)
Uncertainty Analysis in Modelling (UAM) - Coupled Multi-physics and Multi-scale LWR analysis
Critical Issues in Nuclear Reactor Technology (CRISSUE-S)

Related experiments and databases

Results of the Experiments Performed in the PMK-2 Facility for VVER Safety Studies

(Book & CD-ROM ISBN 978-963-05-8461-6 - Akadémiai Kiadó, Budapest)

CCVM: CSNI Code Validation Matrix Integral Test Data
CCVM: CSNI Code Validation Matrix Separate Effects Test Data
PSB-VVER Project: Experiments for transient analysis of VVER-1000 reactors project (abstract)
Sesar Thermal-hydraulics (SETH) Project: PKL and PANDA experiments relevant for accidents management
Cabri Water Loop Project: High burn-up fuel behaviour in RIA conditions (abstract)
RASPLAV Project: Physical and thermal behaviour of the corium in large-scale tests (abstract)
Material Scaling (MASCA) Project: In-vessel phenomena during severe accidents (abstract)
Material Scaling (MASCA phase 2) Project: In-vessel phenomena during severe accidents (abstract)
Melt Coolability and Concrete Interaction (MCCI) Project: MCCI project (abstract)
Phenomena-based Validation Matrix for Ex-vessel (Containment) Models and Codes (Containment-CVM)

For more information, please contact the OECD/NEA Data Bank

Last update: 26 July 2007

For more information on activities managed/supported by the NSC, please contact Claes Nordborg (Claes.Nordborg@oecd.org)

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