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    Activity
    Expert Group on Improvement of Integral Experiments Data for Minor Actinide Management (EGIEMAM-II)

    The expert group works in co-ordination with Working Party on Scientific Issues of Reactor Systems (WPRS) [including the IRPhE Project], Working Party on Scientific Issues of the Fuel Cycle (WPFC) an...

    WPEC NSC Nuclear science Experiments Actinides WPRS Nuclear fuel cycle Reactor physics Fuel cycle physics and chemistry Integral experiments Minor actinides …
    Published date: 9 March 2020
    Activity
    Sodium-cooled Fast Reactor (SFR) Benchmark Task Force

    A sodium-cooled fast reactor (SFR) is a fast neutron reactor that uses molten sodium metal as a coolant. Sodium-cooled Fast Reactors (SFRs) are the most promising type of reactors to achieve Generati...

    Reactor physics EGRPANS Fast reactor WPRS Reactor physics …
    Published date: 4 February 2021
    Activity
    Expert Group on Integral Experiments for Minor Actinide Management (EGIEMAM)

    The expert group critically reviewed integral experiments for validating minor actinide (MA) nuclear data, recommended additional integral experiments needed for validating MA nuclear data and invest...

    WPFC WPEC Nuclear science Experiments Actinides WPRS Reactor physics Integral experiments Minor actinides NSC Nuclear fuel cycle Fuel cycle physics and chemistry …
    Published date: 5 March 2021
    Activity
    Expert Group on Uncertainty Analysis in Modelling (EGUAM)

    The expert group provided advice to the Working Party on Scientific Issues of Reactor Systems (WPRS) on the scientific development needs (data and methods, validation experiments, scenario studies) o...

    EGUAM Boiling water reactors Nuclear science Light water reactors WPRS Reactor physics Modelling and simulation Reactor physics Uncertainty quantification Uncertainty analysis Benchmark Pressurised water reactors …
    Published date: 27 October 2021
    NEA Document
    Benchmark for Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of LWRs - Volume II: Specification and Support Data for the Core Cases (Phase II)
    NEA/NSC/DOC(2012)11

    The objective of the OECD LWR UAM activity is to establish an internationally accepted benchmark framework to compare, assess and further develop different uncertainty analysis methods associated wit...

    English NSC EGRRS WPRS Uncertainty analysis Benchmark …
    Published date: 24 May 2012
    News
    Discussing scientific issues and uncertainty analysis of nuclear reactor systems

    WPRS gathered 172 experts from 22 countries at the annual Benchmark Workshop.

    Nuclear fuel Reactor physics News brief Sodium-cooled reactor Light water reactors EGPRS WPRS Reactor physics Multiphysics …
    Published date: 9 June 2022
    News
    Discussing radiation shielding, novel accelerator experiments and radiation physics simulations

    The event gathered 129 participants from 75 international institutions.

    Reactor physics News brief Nuclear science Radiation shielding EGPRS WPRS Radiation transport and shielding Reactor physics …
    Published date: 6 October 2022
    Event
    20th Meeting of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS)
    20 - 24 February 2023
    NEA headquarters (46, quai Alphonse Le Gallo, 92100 Boulogne-Billancourt, France) with a remote access option

    Under the guidance of the Nuclear Science Committee (NSC), the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performance, an...

    Nuclear science WPRS Multiphysics Radiation transport and shielding Thermal hydraulics and mechanics Reactor physics …
    Published date: 30 January 2023
    Activity
    Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS)

    The Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performance, and radiation transport and shielding in present and future nu...

    Nuclear fuel Reactor physics Multi-physics simulations Fuel studies Light water reactors Thermal hydraulics WPRS Pressurised heavy water reactors Reactor physics Multiphysics …
    Published date: 7 February 2023
    Activity
    Expert Group on Reactor Core Thermal-Hydraulics and Mechanics (EGTHM)

    Created in 2019, under the guidance of the Working Party on Scientific Issues of Reactor Systems (WPRS) the expert group will perform specific tasks associated with core thermal-hydraulics aspects of...

    Reactor physics Sodium-cooled reactor Molten salt reactors Light water reactors Thermal hydraulics WPRS Reactor physics …
    Published date: 2 August 2022
    Publications and Reports
    Review of Integral Experiments for Minor Actinide Management

    Spent nuclear fuel contains minor actinides (MAs) such as neptunium, americium and curium, which require careful management. This becomes even more important when mixed oxide (MOX) fuel is being used...

    English Reactor physics Nuclear science EGPRS WPRS Nuclear science …
    Published date: 17 February 2015
    NEA Document
    Shielding Aspects of Accelerators, Target and Irradiation Facilities (SATIF-12)
    NEA/NSC/R(2015)3

    Twelfth Workshop Proceedings, Batavia, Illinois, United States, 28-30 April 2014

    English Reactor physics NSC Nuclear science Radiation shielding EGPRS WPRS Nuclear science Proceedings Reactor physics …
    Published date: 2 June 2015
    NEA Document
    Shielding Aspects of Accelerators, Target and Irradiation Facilities (SATIF-13) - Proceedings of the Thirteenth Meeting, 10-12 October 2016, Dresden, Germany
    NEA/NSC/R(2018)2
    English Reactor physics NSC Nuclear science Radiation shielding EGPRS WPRS Nuclear science Proceedings Reactor physics …
    Published date: 8 December 2021
    NEA Document
    Shielding Aspects of Accelerators, Targets and Irradiation Facilities (SATIF-14)
    NEA/NSC/R(2021)2

    Proceedings of the Fourteenth Workshop, 30 October-2 November 2018, Gyeongju, Korea.

    English Nuclear science Radiation shielding WPRS Proceedings Reactor physics Reactor physics NSC EGPRS Nuclear science …
    Published date: 16 December 2021
    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
    Benchmarks for Uncertainty Analysis in Modelling (UAM) for the Design, Operation and Safety Analysis of LWRs - Volume I: Specification and Support Data for Neutronics Cases (Phase I)
    NEA/NSC/DOC(2013)7
    English Reactor physics NSC Nuclear science EGPRS WPRS Nuclear science Reactor physics …
    Published date: 16 May 2013
    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
    PBMR Coupled Neutronics/Thermal-Hydraulics Transient Benchmark: The PBMR-400 Core Design - Volume 1: The Benchmark Definition
    NEA/NSC/DOC(2013)10

    This report defines the “OECD/NEA/NSC PBMR Coupled Neutronics/Thermal-hydraulics Transient Benchmark of the PBMR-400 Core Design”. This chapter gives more information on the day-to-day management of ...

    English Nuclear science WPRS Multiphysics Thermal hydraulics and mechanics Reactor physics Multiphysics EGMUP Modelling and simulation Reactor physics NSC Thermal hydraulics Nuclear science Benchmark …
    Published date: 19 June 2013
    Publications and Reports
    VVER-1000 Coolant Transient Benchmark - Phase 2 (V1000CT-2): Summary Results of Exercise 1 on Vessel Mixing Simulation

    Recently developed best-estimate computer code systems for modelling 3-D coupled neutronics/thermal-hydraulics transients in nuclear reactors need to be validated against results from experiments and...

    English Reactor physics Nuclear science WPRS Multiphysics Nuclear science Reactor physics Multiphysics EGMUP …
    Published date: 5 October 2010
    Publications and Reports
    VVER-1000 Coolant Transient Benchmark - Phase 1 Phase I (V1000CT-1), Volume 3: Summary Results of Exercise 2 on Coupled 3-D Kinetics/Core Thermal-hydraulics

    In the field of coupled neutronics/thermal-hydraulics computation there is a need to enhance scientific knowledge in order to develop advanced modelling techniques for new nuclear technologies and co...

    English Reactor physics Nuclear science WPRS Multiphysics Nuclear science Reactor physics Multiphysics EGMUP …
    Published date: 16 November 2007
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