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Characterisation and Transport Modelling of Spent Nuclear Fuel from LWR SMRs

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

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Original languageEnglish
Title of host publicationThe Finnish Nuclear Science and Technology Symposium 2025
Subtitle of host publicationProceedings
Place of PublicationEspoo
PublisherFinnish Nuclear Society
Number of pages9
Publication statusPublished - 22 Oct 2025
MoE publication typeA4 Article in a conference publication
EventFinnish Nuclear Science and Technology Symposium 2025 - Espoo, Finland
Duration: 21 Oct 202522 Oct 2025

Conference

ConferenceFinnish Nuclear Science and Technology Symposium 2025
Country/TerritoryFinland
CityEspoo
Period21/10/2522/10/25

Funding

This work has been enabled by VTT's internal SMR project funded by the Government of Finland.

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

  1. SDG 7 - Affordable and Clean Energy
    SDG 7 Affordable and Clean Energy
  2. SDG 13 - Climate Action
    SDG 13 Climate Action

Keywords

  • Spent nuclear fuel (SNF)
  • Small Modular Reactor (SMR)
  • Burnup calculation
  • Radionuclide release
  • Near-field transport
  • Monte Carlo simulation

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