Sampling, characterization, method validation, and lessons learned in analysis of highly activated stainless steel from reactor decommissioning

Anumaija Leskinen*, Susanna Salminen-Paatero, Jussi Leporanta, Noora Hytönen, Marie Bourgeaux-Goget, Antti Räty

*Corresponding author for this work

Research output: Contribution to journalArticleScientificpeer-review

1 Citation (Scopus)

Abstract

Characterisation of activated reactor components is a multifaceted effort, which include both experimental work and activation calculations which together form a comprehensive characterisation approach. However, both the experimental work and activation calculations have their constraints and uncertainties. This work presents the characterisation of a highly activated stainless steel pipe including sampling planning, sampling, sub-sampling, elemental and radionuclide analyses, and activation calculations. 55Fe, 63Ni and 60Co analyses were carried out in a trilateral intercomparison exercise and the results were compared with activation calculations. The results showed excellent alignment between experimental and activation calculation results.

Original languageEnglish
Pages (from-to)145-163
JournalJournal of Radioanalytical and Nuclear Chemistry
Volume333
DOIs
Publication statusPublished - 2024
MoE publication typeA1 Journal article-refereed

Funding

The authors would like to thank the Finnish Research Programme on Nuclear Waste Management KYT 2022 for funding. FiR1 decommissioning project colleagues for collaboration and provision of studied material.

Keywords

  • Characterisation
  • Decommissioning
  • Difficult to measure radionuclide
  • Easy to measure radionuclide
  • Intercomparison exercise
  • Sampling
  • Stainless-steel

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