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    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
    News
    New edition: the International Handbook of Evaluated Criticality Safety Benchmark Experiments

    The 2021 edition can be downloaded online.

    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
    Pressurised Water Reactor Main Steam-Line Break (MSLB) Benchmark

    This benchmark incorporated full 3-D modelling of the reactor core into system transient codes for best-estimate simulations of the interactions between reactor core behaviour and plant dynamics and ...

    Modelling and simulation Thermal hydraulics Verification and validation Nuclear safety research Uncertainty analysis Safety of components and structures Benchmark Thermal hydraulics and mechanics …
    Published date: 2 August 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
    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
    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
    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
    Activity
    Nuclear Data Sensitivity Tool (NDaST)

     Nuclear Data Sensitivity Tool (NDaST), aims to provide rapid feedback on the effect of changes to nuclear data on integral benchmarks.

    Nuclear science Verification and validation Nuclear data Databases
    Published date: 17 May 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
    International Reactor Physics Handbook Database and Analysis Tool (IDAT)

    The IRPhEP Database and Analysis Tool (IDAT) was first released in 2013 and is included on the IRPhE Handbook DVD. This database and corresponding user interface allows easy access to handbook inform...

    Verification and validation Information, data and knowledge management Databases Reactor physics
    Published date: 17 March 2022
    Activity
    Expert Group on Multi-physics Experimental Data, Benchmarks and Validation (EGMPEBV)

    The expert group dealt with the activities associated with the certification of experimental data and benchmark models along with establishing the processes and procedures for using the data and benc...

    Multi-physics simulations NSC Nuclear science Verification and validation Validation Information, data and knowledge management Nuclear data Benchmark Multiphysics …
    Published date: 23 November 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
    SFCOMPO 2.0 (Spent Fuel Isotopic Composition)

    SFCOMPO 2.0 (Spent Fuel Isotopic Composition) is a relational database designed to facilitate the search and visualisation of experimental assay data of spent nuclear fuel.

    Criticality safety Verification and validation Databases
    Published date: 2 October 2020
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