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    News
    New version released: The NEA Shielding Integral Benchmark Archive and Database (SINBAD)

    The NEA has released version 2 of the Shielding Integral Benchmark Archive and Database (SINBAD), following the migration to a collaborative development environment and a standardised dataset format....

    News brief Transport Experiments Radiation Databases Radiation transport and shielding Reactor physics Integral experiments Verification and validation EGPRS SINBAD Benchmark …
    Published date: 2 July 2025
    Activity
    Nuclear Fuel Cycle Codes Catalogue

    This web page is intended for the description of the nuclear fuel cycle codes that have been used in the recent activities of the Expert Group on Advanced Fuel Cycle Scenarios (EGAFCS), under the gui...

    Nuclear fuel Nuclear science Nuclear data Reactor physics Reactor physics Small modular reactors Advanced reactor systems Nuclear innovation Fuel cycle technology Nuclear science Nuclear fuel cycle Fuel cycle physics and chemistry Fuel cycle economics Sustainable development and nuclear energy …
    Published date: 5 February 2025
    Activity
    Nuclear Fuel Cycle Codes Catalogue - ANICCA

    The Advanced Nuclear Cycle Code, ANICCA, is a nuclear fuel cycle simulation code (NFCSC) that has been developed by SCK-CEN as a flexible tool for nuclear fuel cycle studies. ANICCA is able to simula...

    Nuclear fuel WPFC Nuclear data EGAFCS Nuclear fuel cycle Reactor physics Fuel cycle physics and chemistry …
    Published date: 31 January 2025
    Activity
    Nuclear Fuel Cycle Codes Catalogue - CLASS: Core Library for Advanced Scenario Simulation

    Since 2012, CLASS is developed CNRS/IN2P3 (Centre National de la Recherche Scientifique / Institut National de Physique Nucléaire et de Physique des Particules) with initial support from IRSN (Instit...

    Nuclear fuel EGAFCS Nuclear fuel cycle Reactor physics Fuel cycle physics and chemistry …
    Published date: 4 February 2025
    Activity
    Nuclear Fuel Cycle Codes Catalogue - COSAC

    COSAC is used to study the flow and the storage of nuclear materials in a nuclear fleet composed of the following installations:

    • mines
    • fresh fuel manufacturing plants.
    • reactors
    • cooling pools
    • spent f...
    Nuclear fuel EGAFCS Nuclear fuel cycle Reactor physics Fuel cycle physics and chemistry …
    Published date: 4 February 2025
    Activity
    Nuclear Fuel Cycle Codes Catalogue - COSI

    COSI is a calculation code that simulates nuclear reactor fleets and the associated fuel cycle facilities over several decades. This tool is developed by the SPRC (Reactor Physics and fuel Cycle Serv...

    Nuclear fuel EGAFCS Nuclear fuel cycle Reactor physics Fuel cycle physics and chemistry …
    Published date: 4 February 2025
    Activity
    Nuclear Fuel Cycle Codes Catalogue - DYMOND: Dynamic Model of Nuclear Deployment

    DYMOND simulates the time-dependent behavior and evolution of the entire nuclear fuel cycle including mining, enrichment, fueling, reactors, reprocessing, waste management, disposal, etc.

    Nuclear fuel EGAFCS Nuclear fuel cycle Reactor physics Fuel cycle physics and chemistry …
    Published date: 4 February 2025
    Activity
    Nuclear Fuel Cycle Codes Catalogue - FAMILY-21

    The FAMILY-21 code is a stand-alone simulation code developed to quantitatively indicate reactor systems and nuclear fuel cycle systems adaptable to future uncertain nuclear needs.

    Nuclear fuel EGAFCS Nuclear fuel cycle Reactor physics Fuel cycle physics and chemistry …
    Published date: 4 February 2025
    Activity
    Nuclear Fuel Cycle Codes Catalogue - NFCSS: The Nuclear Fuel Cycle Simulation System

    The Nuclear Fuel Cycle Simulation System (NFCSS) is a scenario based computer simulation tool, implemented in a web based platform, for studying various options of nuclear fuel cycle for nuclear powe...

    Nuclear fuel EGAFCS Nuclear fuel cycle Reactor physics Fuel cycle physics and chemistry …
    Published date: 4 February 2025
    Activity
    Nuclear Fuel Cycle Codes Catalogue - NMB: Nuclear Material Balance

    NMB4.0 is designed to provide flexibility and an all-in-one packaged nuclear fuel cycle simulation for users as open code. Various ideas have been implemented to improve user-friendliness. The main t...

    Nuclear fuel Optimisation of radioactive waste management EGAFCS Nuclear fuel cycle Reactor physics Fuel cycle physics and chemistry …
    Published date: 3 February 2025
    Activity
    Nuclear Fuel Cycle Codes Catalogue - TR_EVOL: Transition Evolution code

    TR_EVOL (Transition Evolution code) fuel cycle simulator is a tool dedicated to the study of mass balances of advanced transition electronuclear scenarios.

    Nuclear fuel EGAFCS Nuclear fuel cycle Reactor physics Fuel cycle physics and chemistry …
    Published date: 31 January 2025
    Activity
    Nuclear Fuel Cycle Codes Catalogue - VISION

    The VISION Nuclear Fuel Cycle Simulation Model is a system dynamics model that captures all aspects of the nuclear fuel cycle, from mining of ore to the ultimate disposal of spent fuel and high-level...

    Nuclear fuel EGAFCS Nuclear fuel cycle Reactor physics Fuel cycle physics and chemistry …
    Published date: 4 February 2025
    Publications and Reports
    NUPEC BWR Full-size Fine-mesh Bundle Test (BFBT) Benchmark

    Refined models for best-estimate calculations based on good-quality experimental data can improve the understanding of phenomena and the quantification of margins for operating nuclear power reactors...

    English Reactor physics Nuclear science Multiphysics Nuclear science Benchmark Reactor physics Multiphysics …
    Published date: 7 July 2006
    Publications and Reports
    NUPEC BWR Full-size Fine-mesh Bundle Test (BFBT) Benchmark - Volume II: Uncertainty and Sensitivity Analyses of Void Distribution and Critical Power - Specification

    This report provides the specification for the uncertainty exercises of the international OECD/NEA, NRC and NUPEC BFBT benchmark problem including the elemental task. The specification was prepared j...

    English Nuclear science Light water reactors WPRS Thermal hydraulics and mechanics EGTHM Reactor physics Modelling and simulation Reactor physics Verification and validation Validation Uncertainty analysis Nuclear science Benchmark …
    Published date: 1 January 2010
    NEA Document
    NUPEC BWR Full-size Fine-mesh Bundle Test BFBT Benchmark - Volume III: Results of Phase I on Void Distribution
    NEA/NSC/R(2020)6

    In the past decade, a large amount of effort has been made towards the direct simulation of the boiling transition (BT) for Boiling Water Reactor (BWR) fuel bundles. This international benchmark, bas...

    English Boiling water reactors Nuclear science Nuclear safety WPRS Thermal hydraulics and mechanics EGTHM Reactor physics Reactor physics Nuclear science Benchmark …
    Published date: 1 June 2021
    NEA Document
    NUPEC BWR Full-size Fine-mesh Bundle Test BFBT Benchmark - Volume IV: Results of Phase II on Pressure Drop and Critical Power
    NEA/NSC/R(2020)7

    In the past decade, a large amount of effort has been made towards the direct simulation of the boiling transition (BT) for boiling water reactor (BWR) fuel bundles. This international benchmark, bas...

    English Boiling water reactors Nuclear science Nuclear safety WPRS EGTHM Reactor physics Reactor physics Nuclear science Benchmark …
    Published date: 2 December 2021
    Activity
    OECD/NRC Benchmark based on NUPEC BWR Full-size Fine-mesh Bundle Tests (BFBT)

    NUPEC Boiling Water Reactor (BWR) Full-size Fine-mesh Bundle Test (BFBT) Benchmark

    Thermal hydraulics Reactor physics
    Published date: 2 August 2022
    NEA Document
    OECD/NRC Benchmark Based on NUPEC Pressurised Water Reactor Sub-channel and Bundle Tests (PSBT) - Volume I: Experimental database and final problem specifications
    NEA/NSC/DOC(2012)1

    Based on the success of the OECD/NRC BFBT Benchmark, Japan released data based on the NUPEC PWR Sub-channel and Bundle Tests (PSBT) Benchmark and asked Pennsylvania State University (PSU) in the Unit...

    English Nuclear science WPRS Multiphysics EGTHM Reactor physics Multiphysics Reactor physics NSC Nuclear science Benchmark Pressurised water reactors …
    Published date: 4 January 2012
    NEA Document
    OECD/NRC Boiling Water Reactor Turbine Trip (TT) Benchmark - Summary of the Fifth Workshop
    NEA/NSC/DOC(2003)1

    21-22 January 2003, Barcelona, Spain

    Reactor physics Boiling water reactors NSC Nuclear science Nuclear science Benchmark Reactor physics Multiphysics …
    Published date: 1 May 2003
    NEA Document
    OECD/NRC Boiling Water Reactor Turbine Trip (TT) Benchmark - Summary of the First Workshop
    NEA/NSC/DOC(2000)22
    Reactor physics Boiling water reactors NSC Nuclear science Nuclear science Benchmark Reactor physics Multiphysics …
    Published date: 10 December 2000
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