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          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

          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

          Type

          Nuclear Science and Engineering

          Year

          2023

          Description

          Neutronic Characterization for a Pressurized Water Reactor Spent Fuel Assembly

          Country/Organization

          Egypt

          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

          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

          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

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