Fir 1 TRIGA activity inventories for decommissioning planning

    Research output: Contribution to journalArticleScientificpeer-review

    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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    title = "Fir 1 TRIGA activity inventories for decommissioning planning",
    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.",
    keywords = "activity inventory, decommissioning, Triga research reactor",
    author = "Antti R{\"a}ty and Petri Kotiluoto",
    year = "2016",
    doi = "10.13182/NT15-86",
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    pages = "28--38",
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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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    AU - Räty, Antti

    AU - Kotiluoto, Petri

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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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