Fir 1 TRIGA activity inventories for decommissioning planning

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2 Citations (Scopus)

Abstract

The objective of the study has been to estimate the residual activity in the decommissioning waste of the TRIGA Mark II-type research reactor FiR 1 in Finland. Neutron flux distributions were calculated with the Monte Carlo code MCNP. These were used in the ORIGEN-S point-depletion code to calculate the neutron-induced activity of materials at different time points by modeling irradiation history and radioactive decay. Knowledge of the radioactive inventory of irradiated materials is important in the planning of the decommissioning activities and is essential for predicting the radiological impact to personnel and the environment. Decommissioning waste consists mainly of ordinary concrete, aluminum, steel, and graphite parts. Results include uncertainties due to assump-tions on material compositions and lack of some detailed operational history data. Comparison to activity inventory estimates of two other decommissioned research reactors is also presented.
Original languageEnglish
Pages (from-to)28-38
JournalNuclear Technology
Volume194
Issue number1
DOIs
Publication statusPublished - 2016
MoE publication typeA1 Journal article-refereed

Fingerprint

Research reactors
Planning
Decommissioning (nuclear reactors)
Neutron flux
Neutrons
Graphite
Irradiation
Personnel
Concretes
Aluminum
Steel
Chemical analysis
Uncertainty

Keywords

  • activity inventory
  • decommissioning
  • Triga research reactor

Cite this

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abstract = "The objective of the study has been to estimate the residual activity in the decommissioning waste of the TRIGA Mark II-type research reactor FiR 1 in Finland. Neutron flux distributions were calculated with the Monte Carlo code MCNP. These were used in the ORIGEN-S point-depletion code to calculate the neutron-induced activity of materials at different time points by modeling irradiation history and radioactive decay. Knowledge of the radioactive inventory of irradiated materials is important in the planning of the decommissioning activities and is essential for predicting the radiological impact to personnel and the environment. Decommissioning waste consists mainly of ordinary concrete, aluminum, steel, and graphite parts. Results include uncertainties due to assump-tions on material compositions and lack of some detailed operational history data. Comparison to activity inventory estimates of two other decommissioned research reactors is also presented.",
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Fir 1 TRIGA activity inventories for decommissioning planning. / Räty, Antti; Kotiluoto, Petri.

In: Nuclear Technology, Vol. 194, No. 1, 2016, p. 28-38.

Research output: Contribution to journalArticleScientificpeer-review

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AB - The objective of the study has been to estimate the residual activity in the decommissioning waste of the TRIGA Mark II-type research reactor FiR 1 in Finland. Neutron flux distributions were calculated with the Monte Carlo code MCNP. These were used in the ORIGEN-S point-depletion code to calculate the neutron-induced activity of materials at different time points by modeling irradiation history and radioactive decay. Knowledge of the radioactive inventory of irradiated materials is important in the planning of the decommissioning activities and is essential for predicting the radiological impact to personnel and the environment. Decommissioning waste consists mainly of ordinary concrete, aluminum, steel, and graphite parts. Results include uncertainties due to assump-tions on material compositions and lack of some detailed operational history data. Comparison to activity inventory estimates of two other decommissioned research reactors is also presented.

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