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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
Activity
Pressurised Water Reactor MOX/UO2 Core Transient Benchmark

PWR MOX/UO2 Core Transient Benchmark

Verification Benchmark Reactor physics
Published date: 7 December 2022
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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 Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook

The International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook contains criticality safety benchmark specifications that have been derived from experiments that were performed at...

Modelling and simulation Criticality safety Verification and validation Verification Benchmark …
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
Forsmark 1 and 2 Boiling Water Reactor Stability Benchmark

Forsmark 1 and 2 Boiling Water Reactor Stability Benchmark

Verification and validation Verification Reactor physics
Published date: 2 August 2022
Activity
VVER-1000 Coolant Transient (V1000CT) Benchmarks

The overall objective of the VVER-1000 Coolant Transient (V1000CT) Benchmark was to assess computer codes used in the safety analysis of water-water energetic reactor (VVER) power plants, specificall...

Verification Multiphysics Benchmark Reactor physics Pressurised water reactors …
Published date: 2 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