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.

Keywords

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

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