WPRS Expert Group on Uncertainty Analysis in Modelling (EGUAM)

EGUAM mandate

Recent/current activities

Publications

Volume VIII - Benchmark exercise on kinetics parameters based on comparison with experimental results from the CROCUS facility - Spring 2007 (included also in IRPhE Handbook)
MOX/UOX-core control rod ejection benchmark - January 2007.
Boiling Water Reactor Turbine Trip (BWRTT) Benchmark:

Volume IV: Best-Estimate Coupled 3-D Core/Thermal-Hydraulic System Modeling

VVER-1000 Coolant Transient Benchmarks Phase 1 (V1000CT-1):

Volume III: Coupled 3-D Kinetics/Core Thermal-Hydraulic Response Evaluation
Volume IV: Best-Estimate Coupled 3-D Core/Thermal-Hydraulic Plant Transient Modeling

VVER-1000 Coolant Transient Benchmarks Phase 2 (V1000CT-2):

Volume I: Specifications of the VVER-1000 Vessel Mixing Problem
Volume II: Main Steam-Line Break (MSLB) Problem Specification
Volume III: Comparison of Computational Fluid Dynamics and Coarse Mesh Calculations with Measured Data
Volume IV: MSLB Coupled 3D Neutronics / Vessel TH Simulation
Volume V: MSLB Best Estimate Coupled Simulation

PBMR Coupled Neutronics/Thermal Hydraulics Transient Benchmark the PBMR-400 Core Design :
- Volume I: Benchmark Definition
- Volume II: Steady State Benchmark
- Volume III: Transient Benchmark
PRIMO Ramped MOX Fuel Rod BD8 Benchmark
Uncertainty Analysis in Modelling:

Volume I: Neutronics Phase Specification
Volume II: Neutronics Phase Results

Related Benchmarks

UAM-LWR: Uncertainty analysis in modelling - LWRs
BFBT: NUPEC BWR Full-size Fine-mesh Bundle Tests Benchmark
PSBT: NUPEC PWR Sub-Channel Bundle Tests Benchmark
V1000CT: VVER-1000 Coolant Transient Benchmarks
KALININ3 VVER-100 Coolant Transient Benchmarks
PBMR-400: PBMR Coupled Neutronics/Thermal Hydraulics Transient Benchmark
Boiling Water Reactor Turbine Trip (BWRTT)
Benchmark Specification for HTGR Fuel Element Depletion

Previously completed or related activities

Expert Group on Reactor Stability and LWR Transient Benchmarks

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
Critical Issues in Nuclear Reactor Technology (CRISSUE-S)

PWR MOX/UO2 Core Transient Benchmark (completed)

Workshops

PSBT-1: April 12-13, 2010 - Hosted by the University of Pisa, Italy.
PSBT-2: April 11-12, 2011 - Hosted by the Royal Institute of Technology (Kungliga Tekniska Högskolan, KTH) Stockholm, Sweden.

UAM-4, Fourth Workshop, 14-16 April 2010, hosted by the University of Pisa, Italy.
UAM-5, Fifth Workshop, 13-15 April 2011, hosted by the Royal Institute of Technology, Stockholm, Sweden.

Meetings, workshops and conferences

WPRS and associated Expert Group meetings are held approximately every twelve months. The ninth meeting of the WPRS (WPRS-09) and associated Expert Group meetings took place on 13-17, February 2012 at the OECD Headquarters, Issy-les-Moulineaux, France. More about WPRS meetings.

Contact

For more information on WPRS, please contact:

For more information on activities managed/supported by the NSC, please contact:

Last reviewed: 26 March 2012