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  • Testing and Simulation for Advanced Technology and Accident Tolerant Fuels (ATF-TS)

    Closed for proposals

    Project Type

    Coordinated Research Project

    Project Code

    T12032

    CRP

    2236

    Approved Date

    12 December 2019

    Status

    Active - Ongoing

    Start Date

    6 April 2020

    Expected End Date

    31 December 2024

    Completed Date

    26 May 2025

    Participating Countries

    Argentina
    Belarus
    Belgium
    Brazil
    Bulgaria
    Canada
    China
    Czech Republic
    France
    Germany
    Hungary
    Iran (Islamic Republic of)
    Italy
    Japan
    Poland
    Republic of Korea
    Russian Federation
    Slovakia
    Spain
    United Kingdom of Great Britain and Northern Ireland
    United States of America

    Description

    The proposed CRP will support interested IAEA Member States in their efforts to design and develop Accident Tolerant and Advanced Technology Fuels (ATF) for light water reactors (LWRs) to enhance the safety and sustainability of nuclear power. The design, fabrication and in-pile behaviour of currently operated and innovative nuclear fuels and materials to enable a reliable and safe operation of nuclear power plants is a recurrent priority of IAEA’s sub-programme "Nuclear Power Reactor Fuel Engineering". Development and validation of computer codes for fuel design and in-pile behaviour analysis under normal and off-normal conditions (including Design Extension Conditions, DEC) are possible only if high-quality experimental data are made available. That is why international cooperation in this area is highly desirable, and in particular among IAEA Member States interested in enhancing their computer code capabilities to predict nuclear fuel behaviour under Design Basis (DB) and Design Extension (DE) Conditions.
    The CRP will bring together specialists from IAEA MSs with active ATF R&D programmes to share their national efforts and to?contribute in any of the following objectives of the CRP:
    Round Robin tests on different ATF cladding concepts (e.g. coated Zr cladding, FeCrAl, SiC);
    Bundle tests under DB/DEC with ATF materials (e.g. with coated Zry-4 rods under SA and/or LOCA conditions);
    Collection of irradiation tests data;
    Code benchmarking against existing data, relevant for advanced fuel and cladding concepts from other experimental Programmes, as well as new tests data obtained during the CRP;
    LOCA evaluation methodology development for NPP applications including uncertainty and sensitivities studies.

    Objectives

    To support Member States to understand and address factors affecting the design, fabrication and in-pile behaviour of currently operating and innovative nuclear fuels and materials for power reactors, to increase technology readiness for candidate ATF materials.

    Specific objectives

    To perform experimental tests including single rod and bundle tests on ATFs' performance under normal, DB and DE conditions

    To benchmark fuel codes against new test data either obtained during the CRP or from existing data relevant to advanced fuel and cladding concepts from Member States' experimental Programmes.

    To develop LOCA evaluation methodology for ATF performance with a view for NPP applications.

    To perform experimental tests including single rod and bundle tests on ATFs' performance under normal, DB and DE conditions

    To benchmark fuel codes against new test data either obtained during the CRP or from existing data relevant to advanced fuel and cladding concepts from Member States' experimental Programmes.

    To develop LOCA evaluation methodology for ATF performance with a view for NPP applications.

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