Radiological characterization of the activation of the structure materials of the BR1 research reactor

    Research outputpeer-review

    Abstract

    This paper presents a radiological characterization of structure materials of the BR1 research reactor. BR1 is a natural uranium fuelled, graphite moderated and gas (air) cooled reactor. The objectives of this study are (1) to predict the type and the quantity of activation products (isotope-by-isotope) formed over the operating life of the reactor BR1 and remaining after a given cooling time and (2) to evaluate the structure materials activation (, or activations) at different time scales after the definitive predicted shutdown of the reactor. For this purpose, a calculation methodology was defined: The SCALE4.3 code system, in conjunction with the 238 neutron group library (based on ENDF/B-V data file) was used to generate cross section for all relevant materials. For the 2-dimensional spatial flux determination, the neutron transport code DORT was used. From the 2-D flux map, activations are obtained by using the ORIGEN2 code and taking into account the detailed operational history. This work concerns both the graphite (reflector) and the concrete (biological shielding) of the BR1 reactor. Main results are as follows: we notice that in the concrete and the graphite, the flux is almost thermal (more than 90% of total flux has energy below 0.5 eV), so this enhances the thermal activation reactions such as40Ca(n,)41Ca,54Fe(n,)55Fe, etc. For the graphite zone,14C remains the dominating participant to the activity after 5 years of cooling time. There is also production of other activation products such as55Fe and63Ni. In graphite, we underline the generation of60Co formed by capture reaction on Fe and Ni (Fe and Ni are initially present in graphite as impurities),60Co is a high energy gamma emitter. For concrete,133Ba is by far the principal producer of activity but we underline also55Fe and41Ca contributions:55Fe is the most active during the first years of cooling time and the41Ca contribution becomes more significant after a long term scale. In concrete, the specific activity is strongly spatially dependent.

    Original languageEnglish
    Title of host publicationProceedings of the PHYSOR 2000 - ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium
    PublisherAmerican Nuclear Society
    ISBN (Electronic)0894486551, 9780894486555
    StatePublished - 2000
    Event2000 ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium, PHYSOR 2000 - Pittsburgh
    Duration: 7 May 202012 May 2020

    Publication series

    NameProceedings of the PHYSOR 2000 - ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium

    Conference

    Conference2000 ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium, PHYSOR 2000
    Country/TerritoryUnited States
    CityPittsburgh
    Period2020-05-072020-05-12

    ASJC Scopus subject areas

    • Nuclear Energy and Engineering
    • Nuclear and High Energy Physics
    • Radiation
    • Safety, Risk, Reliability and Quality

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