Validation and Optimization of Activity Estimates of the FiR 1 TRIGA Research Reactor Biological Shield Concrete

Antti Räty (Corresponding Author), Merja Tanhua-Tyrkkö, Petri Kotiluoto, Tommi Kekki

Research output: Contribution to journalArticleScientificpeer-review

2 Citations (Scopus)

Abstract

FiR 1 is a TRIGA Mark II-type research reactor in Finland. It was in operation between 1962 to 2015 and will be dismantled in 2022 to 2023. Preliminary calculations of the activities in the reactor main structures were performed in an earlier stage of the decommissioning project. Samples of the activated parts of the reactor biological shield concrete were drilled in December 2018 to validate these estimates. This paper describes the calculations and gamma activity measurements performed for the activated concrete samples to determine the boundary between radioactive parts and concrete that can plausibly be free-released from regulatory control. The activities have been estimated with a two-step calculation process using the MCNP and ORIGEN-S calculation codes and measurements using an ISOCS gamma spectrometer with a high-purity germanium detector.

Original languageEnglish
Pages (from-to)735-750
Number of pages16
JournalNuclear Science and Engineering
Volume196
Issue number6
DOIs
Publication statusPublished - 2022
MoE publication typeA1 Journal article-refereed

Keywords

  • Concrete
  • ISOCS
  • MCNP
  • ORIGEN-S
  • TRIGA

Fingerprint

Dive into the research topics of 'Validation and Optimization of Activity Estimates of the FiR 1 TRIGA Research Reactor Biological Shield Concrete'. Together they form a unique fingerprint.

Cite this