• <menu id="888u4"><menu id="888u4"></menu></menu>
  • Spent Fuel Characterization

    Closed for proposals

    Project Type

    Coordinated Research Project

    Project Code

    T13018

    CRP

    2239

    Approved Date

    23 June 2020

    Status

    Closed

    Start Date

    12 August 2020

    Expected End Date

    31 December 2024

    Completed Date

    3 March 2025

    Participating Countries

    Argentina
    Belgium
    Egypt
    Finland
    France
    Lithuania
    Mexico
    Republic of Korea
    Romania
    Slovenia
    Spain
    Sweden
    Switzerland
    Ukraine
    United Kingdom of Great Britain and Northern Ireland

    Description

    In order to assess the ability of spent fuel assemblies to meet the requirements for transition from one back end fuel cycle step to another, certain characteristics have to be known to support safety and technical assessments.
    The CRP will address the work currently being undertaken to determine the characteristics of spent fuel to ensure its safe management throughout storage, transport and disposal.

    Objectives

    The overall objective of this Coordinated Research Project is to support and share information between concerned Member States on issues related to the characterization of spent nuclear fuel in the various steps of its management. This will be achieved by gathering information from Member States regarding the approaches to characterization they have taken and are developing for the various steps of SFM, including the validation of models, techniques and procedures, enabling the exchange of information and experiences between Member States with a greater maturity in this area with Member States with limited experience and infrastructures, aiming at compiling this information in an IAEA Technical Report as the CRP output.

    Specific objectives

    Collecting and exchanging information from Member States on the methods they currently use for characterizing spent fuel at the various steps of SFM and how they have been validated.

    Sharing information on techniques, systems and codes under development, and their plans for subsequent validation.

    Identifying the potential for collaborative work between Institutes.

    Enhancing the maturity of knowledge in MSs with limited experience.

    Enhance participation of young experts.

    Collecting and exchanging information from Member States on the methods they currently use for characterizing spent fuel at the various steps of SFM and how they have been validated.

    Sharing information on techniques, systems and codes under development, and their plans for subsequent validation.

    Identifying the potential for collaborative work between Institutes.

    Enhancing the maturity of knowledge in MSs with limited experience.

    Enhance participation of young experts.

    Impact

    The CRP raised partners’ awareness on the topic and allowed them to share their own knowledge and learn what other countries/organizations were doing on the same topical area. Especially during the RCMs, in Sweden and the UK, the technical visits helped a lot demonstrate why characterization of SNF is such an important topic. Regarding the link to the EURAD project, the impact of the CRP was to bring the international perspective to a European project through the members participating in both projects.

    Relevance

    The CRP's topic is as relevant today as it was when the project was launched, and many participating countries realized through this project that there are valuable lessons to be learned, which will significantly improve their projects.

    CRP Publications

    Type

    The 2023 Water Reactor Fuel Performance Meeting (WRFPM2023)

    Year

    2023

    Description

    Evaluation of SCALE code cross-section processing options for RBMK simulations

    Country/Organization

    Lithuania

    Type

    Nuclear Science and Engineering

    Year

    2023

    Publication URL

    https://www.researchgate.net/publication/373042460_Neutronic_Characterization_fo…

    Description

    Neutronic Characterization for a Pressurized Water Reactor Spent Fuel Assembly

    Country/Organization

    Egypt

    Type

    PhD Thesis Virginie Solans

    Year

    2024

    Publication URL

    https://uu.diva-portal.org/smash/record.jsf?pid=diva2%3A1887995&dswid=7684

    Description

    Analysis of Gamma and Neutron Emission for Predicting Decay Heat in Spent Nuclear Fuel

    Country/Organization

    Sweden

    Type

    Nuclear Science and Engineering

    Year

    2023

    Description

    Neutronic Characterization for a Pressurized Water Reactor Spent Fuel Assembly

    Country/Organization

    Egypt

    Type

    Conference proceedings, HOTLAB 2021 - Annual Meeting on Hot Laboratories and Remote Handling, Prague, Czech Republic, September 26-30, 2021

    Year

    2021

    Publication URL

    https://hotlab.sckcen.be/proceedings

    Description

    Non-destructive Method for Measurement of Oxide Layer Thickness on Irradiated Fuel Rods, Maren Mincu

    Country/Organization

    Romania RATEN

    Type

    The 2023 Water Reactor Fuel Performance Meeting (WRFPM2023)

    Year

    2023

    Publication URL

    https://doi.org/10.1016/j.net.2022.08.001

    Description

    Evaluation of SCALE code cross-section processing options for RBMK simulations

    Country/Organization

    Lithuania

    Stay in touch

    Newsletter

    午夜爱爱爱爱爽爽爽视频网站