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    Estimate of Neutron Fluence Using Isotope Ratio Method for ZR-2.5NB Materials Irradiated in the National Research Universal Reactor

    Source: Journal of Nuclear Engineering and Radiation Science:;2023:;volume( 009 ):;issue: 003::page 34501-1
    Author:
    Wang, Xiaolin
    ,
    Shi, Youqing
    ,
    Bickel, Grant
    ,
    Robert, DeAbreu
    DOI: 10.1115/1.4055931
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The isotope ratio method (IRM) is a technique used for estimating the energy production in a fission reactor by measuring isotope ratios in nonfuel reactor components. This method has been successfully demonstrated on the estimation of cumulative energy production as well as plutonium production in graphite-moderated and light-water-moderated reactors for nonproliferation purposes. In this paper, IRM was used to estimate neutron fluence in Zr-2.5Nb materials irradiated in fast neutron (FN) irradiation facilities in the National Research Universal (NRU) reactor. Neutron fluence has been shown to be an important parameter for studying irradiation effects on the performance and properties of critical reactor components. Selected isotope ratios of hafnium and iron were used as indicators of the neutron fluence in Zr-2.5Nb sample materials. Correlations between neutron fluence and the indicator element isotope ratios were generated using the reactor physics simulation codes Winfrith improved multigroup scheme (WIMS)-AECL and SCALE/Oak Ridge Isotope GENeration code (ORIGEN). Inductively coupled plasma-mass spectrometry (ICP-MS) was used to obtain accurate measurements of the isotope ratios. Neutron fluence values estimated using IRM, were in good agreement with the values based on measured irradiation power histories of the NRU reactor. This study proposes a potential application of IRM to the estimation of neutron fluence for critical reactor components in heavy-water-moderated reactors such as pressure and calandria tubes in CANDU® reactors.
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      Estimate of Neutron Fluence Using Isotope Ratio Method for ZR-2.5NB Materials Irradiated in the National Research Universal Reactor

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4294881
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    contributor authorWang, Xiaolin
    contributor authorShi, Youqing
    contributor authorBickel, Grant
    contributor authorRobert, DeAbreu
    date accessioned2023-11-29T19:35:32Z
    date available2023-11-29T19:35:32Z
    date copyright2/8/2023 12:00:00 AM
    date issued2/8/2023 12:00:00 AM
    date issued2023-02-08
    identifier issn2332-8983
    identifier otherners_009_03_034501.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4294881
    description abstractThe isotope ratio method (IRM) is a technique used for estimating the energy production in a fission reactor by measuring isotope ratios in nonfuel reactor components. This method has been successfully demonstrated on the estimation of cumulative energy production as well as plutonium production in graphite-moderated and light-water-moderated reactors for nonproliferation purposes. In this paper, IRM was used to estimate neutron fluence in Zr-2.5Nb materials irradiated in fast neutron (FN) irradiation facilities in the National Research Universal (NRU) reactor. Neutron fluence has been shown to be an important parameter for studying irradiation effects on the performance and properties of critical reactor components. Selected isotope ratios of hafnium and iron were used as indicators of the neutron fluence in Zr-2.5Nb sample materials. Correlations between neutron fluence and the indicator element isotope ratios were generated using the reactor physics simulation codes Winfrith improved multigroup scheme (WIMS)-AECL and SCALE/Oak Ridge Isotope GENeration code (ORIGEN). Inductively coupled plasma-mass spectrometry (ICP-MS) was used to obtain accurate measurements of the isotope ratios. Neutron fluence values estimated using IRM, were in good agreement with the values based on measured irradiation power histories of the NRU reactor. This study proposes a potential application of IRM to the estimation of neutron fluence for critical reactor components in heavy-water-moderated reactors such as pressure and calandria tubes in CANDU® reactors.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleEstimate of Neutron Fluence Using Isotope Ratio Method for ZR-2.5NB Materials Irradiated in the National Research Universal Reactor
    typeJournal Paper
    journal volume9
    journal issue3
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4055931
    journal fristpage34501-1
    journal lastpage34501-5
    page5
    treeJournal of Nuclear Engineering and Radiation Science:;2023:;volume( 009 ):;issue: 003
    contenttypeFulltext
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