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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
News
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
Activity
Deterministic Time-Dependent Neutron Transport Benchmark without Spatial Homogenisation (C5G7-TD)

To ensure reliable modelling of neutron physics within a state-of-the-art transient code, the neutron kinetics part of such a code should be based on the full-scale calculation of the space-time neu...

Transport Verification and validation Verification Radiation Uncertainty quantification Uncertainty analysis Benchmark Reactor physics …
Published date: 19 July 2022
Activity
KALININ-3 Coolant Transient Benchmark

This benchmark was a continuation of the V1000CT activities and defined a coupled code problem for further validation of thermal-hydraulics system codes for application with Russian-designed VVER-100...

Verification and validation Verification Benchmark Reactor physics
Published date: 19 July 2022
Activity
Boiling Water Reactor Turbine Trip (BWRTT) Benchmark

The Boiling Water Reactor Turbine Trip (BWRTT) Benchmark was established to challenge the coupled system thermal-hydraulic/neutron kinetics codes against a Peach-Bottom-2 (a GE-designed BWR/4) turbin...

Thermal hydraulics Verification and validation Verification Uncertainty quantification Uncertainty analysis Reactor physics …
Published date: 19 July 2022
Activity
IRPhE primary documentation

Collected sources of primary documentation for reactor physics benchmarks.

Modelling and simulation Reactor physics Verification and validation Verification Validation Benchmark Reactor physics …
Published date: 14 April 2022
Activity
Pebble Bed Modular Reactor (PBMR) Coupled Neutronics/Thermal-hydraulics Transients Benchmark - PBMR-400 Core Design

The international benchmark concerned pebble bed modular reactor (PBMR) coupled neutronics/thermal-hydraulics transients based on the PBMR-400MW design.

SMR Gas-cooled reactors Thermal hydraulics Verification Multiphysics Benchmark Reactor physics Multiphysics …
Published date: 26 July 2021
Activity
Fluoride Salt-Cooled High-Temperature Reactor (FHR) Benchmark

Fluoride salt-cooled high-temperature reactors (FHRs), cooled with liquid (molten) salt, fueled with TRISO-based fuel are a potential molten salt reactor (MSR) design.

Nuclear science Molten salt reactors Verification Reactor physics
Published date: 14 June 2021
NEA Document
Benchmark Specifications for the Fluoride-salt High-temperature Reactor (FHR) Reactor Physics Calculations
NEA/NSC/R(2020)5

This benchmark focuses on FHR reactors with plates and triso fuel. Several phases are planned, starting with neutronics on a simple fuel element simulation without burn-up, and gradually extending to...

Reactor physics Verification Reactor physics
Published date: 4 June 2021
Subtopic
Thermal hydraulics and mechanics

Thermal hydraulics and mechanics deals with the physics and mechanics of the flow and energetic transfer of liquids, and its interactions with the structures around them in large complex systems, suc...

Reactor physics Nuclear science Thermal hydraulics Verification and validation Verification Validation Benchmark Reactor physics …
Published date: 10 December 2020
Activity
Subgroup on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of Sodium-cooled Fast Reactors (SFR-UAM)

The Subgroup on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of Sodium-cooled Fast Reactors (SFR-UAM) was formed to check the use of best-estimate codes and data....

Sodium-cooled reactor Verification Fast reactor Benchmark Reactor physics …
Published date: 6 November 2020
Activity
MeshTal Viewer

MeshTal Viewer is a Java based software which can read mesh tallies output formats of several neutron transport codes and display them graphically.

Nuclear science Verification
Published date: 2 October 2020