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Burst Fission Gas Release (FGR) Benchmark of the Expert Group on Reactor Fuel Performance (EGRFP)

This benchmark is organised to examine the models for fission gas release during anticipated operational occurrences (AOOs).

Nuclear science Validation EGRPF WPRS Benchmark Reactor fuel performance …
Published date: 7 March 2023
Activity
Lead-cooled Fast Reactor Benchmark (LFR)

Lead-cooled Fast Reactors (LFR) are rather new concepts which have gathered increasing international attention after the Generation-IV International Forum (GIF) selected them as promising candidates ...

Generation IV reactors Verification and validation Verification Validation Liquid metal reactors Benchmark Reactor physics …
Published date: 31 January 2023
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Modelling and simulation Criticality safety Criticality Verification and validation Verification Validation ICSBEP Benchmark …
Published date: 22 November 2022
Activity
IRPhE Technical Review Group

The International Reactor Physics Experiment Evaluation (IRPhE) Technical Review Group provides the nuclear community with qualified benchmark data sets by collecting reactor physics experimental dat...

Modelling and simulation Reactor physics Verification and validation Verification Validation Benchmark Reactor physics …
Published date: 10 November 2022
Activity
International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhE)

The International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhE) contains reactor physics benchmark specifications that have been derived from experiments that were performed at ...

Modelling and simulation Reactor physics Verification and validation Verification Validation Benchmark Reactor physics …
Published date: 9 November 2022
Activity
Thermal hydraulic code validation benchmark for high temperature gas-cooled reactors using HTTF data (HTGR T/H)

High-temperature gas-cooled nuclear reactors are one of the next generation reactor designs. This benchmark consists consists in a multi-staged code-to-code-to-data thermal hydraulics code validation...

Thermal hydraulics Verification and validation Verification Validation Benchmark Reactor physics …
Published date: 9 November 2022
Activity
SINBAD - Shielding Integral Benchmark Archive and Database

The Shielding Integral Benchmark Archive and Database (SINBAD) database contains compilations for 46 reactor shielding, 31 fusion neutronics and 23 accelerator shielding experiments.

Transport Experiments Radiation Validation Databases Benchmark Radiation transport and shielding Reactor physics …
Published date: 4 August 2022
Activity
Liquid Metal Fast Reactor Core Thermal-Hydraulics Benchmark (LMFR T/H)

The Liquid Metal Fast Reactor (LFMR) is one of the next generation reactor designs. This benchmark consists of steady-state numerical predictions of Texas A&M University (TAMU) separate effect tests ...

Thermal hydraulics Verification and validation Verification Validation Benchmark Reactor physics …
Published date: 19 July 2022
Activity
McMaster Core Thermal-Hydraulics Benchmark

Building on the NEA BFBT and PSBT benchmarks, McMaster University, in collaboration with North Carolina State University, launched a CANDU thermal-hydraulic benchmark under the WPRS Expert Group on U...

Nuclear science Thermal hydraulics Verification and validation Validation Benchmark Reactor physics …
Published date: 19 July 2022
Activity
Benchmark for Uncertainty Analysis in Best-Estimate Modelling for Design, Operation and Safety Analysis of Light Water Reactors (LWR-UAM)

The goal of the Benchmark for Uncertainty Analysis in Best-Estimate Modelling for Design, Operation and Safety Analysis of Light Water Reactors (LWR-UAM) is to determine the uncertainty in light wate...

Modelling and simulation Reactor physics Light water reactors Verification and validation Validation Uncertainty quantification Uncertainty analysis Benchmark Reactor physics Pressurised water reactors …
Published date: 5 July 2022