Preliminary Waste Characterization Measurements in FiR 1 TRIGA Research Reactor Decommissioning Project

    Research output: Contribution to journalArticleScientificpeer-review

    1 Citation (Scopus)

    Abstract

    The objective of the study has been to verify the calculated residual activity in the decommissioning waste of the TRIGA Mark II–type research reactor FiR 1 in Finland. Knowledge of the radioactive inventory of irradiated materials is important in the planning of decommissioning activities and is essential for predicting the radiological impact to personnel and the environment. Measurements are performed for low active material samples from outer parts of the reactor. Methods include gamma spectrometric measurements, composition measurements with mass spectrometry, oxidation measurements of especially 14C in graphite, and full combustion measurements of lithium-enriched shielding materials. Results are compared to estimates calculated with a combined Monte Carlo model of the reactor and a point-depletion code modeling the irradiation history. Decommissioning waste consists mainly of ordinary concrete, aluminum, steel, and graphite parts. Only preliminary measurements of low active samples are reported so far, but the same methods will be used later for characterizing and classifying dismantling waste. Some discussion of characterization requirements and future sampling is also included.

    Original languageEnglish
    Pages (from-to)205-220
    Number of pages16
    JournalNuclear Technology
    Volume203
    Issue number2
    DOIs
    Publication statusPublished - 3 Aug 2018
    MoE publication typeA1 Journal article-refereed

    Fingerprint

    Decommissioning (nuclear reactors)
    decommissioning
    Research reactors
    reactors
    Graphite
    graphite
    Finland
    personnel
    classifying
    Shielding
    Mass spectrometry
    shielding
    planning
    depletion
    Lithium
    mass spectroscopy
    lithium
    sampling
    histories
    Irradiation

    Keywords

    • activity inventory, characterization
    • Decommissioning
    • TRIGA research reactor

    Cite this

    @article{ce3d384d3a2242bca5564a5414ffdd93,
    title = "Preliminary Waste Characterization Measurements in FiR 1 TRIGA Research Reactor Decommissioning Project",
    abstract = "The objective of the study has been to verify the calculated residual activity in the decommissioning waste of the TRIGA Mark II–type research reactor FiR 1 in Finland. Knowledge of the radioactive inventory of irradiated materials is important in the planning of decommissioning activities and is essential for predicting the radiological impact to personnel and the environment. Measurements are performed for low active material samples from outer parts of the reactor. Methods include gamma spectrometric measurements, composition measurements with mass spectrometry, oxidation measurements of especially 14C in graphite, and full combustion measurements of lithium-enriched shielding materials. Results are compared to estimates calculated with a combined Monte Carlo model of the reactor and a point-depletion code modeling the irradiation history. Decommissioning waste consists mainly of ordinary concrete, aluminum, steel, and graphite parts. Only preliminary measurements of low active samples are reported so far, but the same methods will be used later for characterizing and classifying dismantling waste. Some discussion of characterization requirements and future sampling is also included.",
    keywords = "activity inventory, characterization, Decommissioning, TRIGA research reactor",
    author = "Antti R{\"a}ty and Tommi Kekki and Merja Tanhua-Tyrkk{\"o} and Tiina Lavonen and Emmi Myllykyl{\"a}",
    year = "2018",
    month = "8",
    day = "3",
    doi = "10.1080/00295450.2018.1445402",
    language = "English",
    volume = "203",
    pages = "205--220",
    journal = "Nuclear Technology",
    issn = "0029-5450",
    publisher = "American Nuclear Society ANS",
    number = "2",

    }

    TY - JOUR

    T1 - Preliminary Waste Characterization Measurements in FiR 1 TRIGA Research Reactor Decommissioning Project

    AU - Räty, Antti

    AU - Kekki, Tommi

    AU - Tanhua-Tyrkkö, Merja

    AU - Lavonen, Tiina

    AU - Myllykylä, Emmi

    PY - 2018/8/3

    Y1 - 2018/8/3

    N2 - The objective of the study has been to verify the calculated residual activity in the decommissioning waste of the TRIGA Mark II–type research reactor FiR 1 in Finland. Knowledge of the radioactive inventory of irradiated materials is important in the planning of decommissioning activities and is essential for predicting the radiological impact to personnel and the environment. Measurements are performed for low active material samples from outer parts of the reactor. Methods include gamma spectrometric measurements, composition measurements with mass spectrometry, oxidation measurements of especially 14C in graphite, and full combustion measurements of lithium-enriched shielding materials. Results are compared to estimates calculated with a combined Monte Carlo model of the reactor and a point-depletion code modeling the irradiation history. Decommissioning waste consists mainly of ordinary concrete, aluminum, steel, and graphite parts. Only preliminary measurements of low active samples are reported so far, but the same methods will be used later for characterizing and classifying dismantling waste. Some discussion of characterization requirements and future sampling is also included.

    AB - The objective of the study has been to verify the calculated residual activity in the decommissioning waste of the TRIGA Mark II–type research reactor FiR 1 in Finland. Knowledge of the radioactive inventory of irradiated materials is important in the planning of decommissioning activities and is essential for predicting the radiological impact to personnel and the environment. Measurements are performed for low active material samples from outer parts of the reactor. Methods include gamma spectrometric measurements, composition measurements with mass spectrometry, oxidation measurements of especially 14C in graphite, and full combustion measurements of lithium-enriched shielding materials. Results are compared to estimates calculated with a combined Monte Carlo model of the reactor and a point-depletion code modeling the irradiation history. Decommissioning waste consists mainly of ordinary concrete, aluminum, steel, and graphite parts. Only preliminary measurements of low active samples are reported so far, but the same methods will be used later for characterizing and classifying dismantling waste. Some discussion of characterization requirements and future sampling is also included.

    KW - activity inventory, characterization

    KW - Decommissioning

    KW - TRIGA research reactor

    UR - http://www.scopus.com/inward/record.url?scp=85048131548&partnerID=8YFLogxK

    U2 - 10.1080/00295450.2018.1445402

    DO - 10.1080/00295450.2018.1445402

    M3 - Article

    AN - SCOPUS:85048131548

    VL - 203

    SP - 205

    EP - 220

    JO - Nuclear Technology

    JF - Nuclear Technology

    SN - 0029-5450

    IS - 2

    ER -