Preliminary core and fuel design of bwr with multi-Axial fuel shuffling

Yudai Tasaki, Akifumi Yamaji

    Research output: Chapter in Book/Report/Conference proceedingConference contribution

    Abstract

    The concept of "multi-Axial fuel shuffling" has been recently proposed for a high breeding core design of supercritical-water cooled reactor. In this study, the same design principle is applied to boiling water reactor (BWR) condition. The results show that the Compound System Doubling Time (CSDT) can be reduced by increasing fuel batch number of the upper blanket layer, but more investigations may be necessary to consider further improvement of the core breeding performance. Moreover, fuel performance of the axially heterogeneous core has been evaluated with the power history obtained by the core calculations and modified FEMAXI-7 code which consider two different types of pellets (i.e., MOX and depleted uranium) within one fuel rod. The analysis results indicate that uncertainty in thermal conductivity of MOX pellets may be important in evaluating the peak pellet temperature, while relatively large plenum volume may be required at the bottom of the fuel rod to accommodate the large amount of fission gas release. Another potential design issue may be the cladding outer diameter increase by the MOX pellet swelling, which may have significant influence on evaluation of MCHFR.

    Original languageEnglish
    Title of host publicationProceedings of the 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018
    PublisherAmerican Nuclear Society
    Pages1144-1152
    Number of pages9
    ISBN (Electronic)9780894487552
    Publication statusPublished - 2018 Jan 1
    Event2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018 - Charlotte, United States
    Duration: 2018 Apr 82018 Apr 11

    Other

    Other2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018
    CountryUnited States
    CityCharlotte
    Period18/4/818/4/11

    Fingerprint

    Water cooled reactors
    Boiling water reactors
    Uranium
    Swelling
    Thermal conductivity
    Gases
    Temperature
    Uncertainty

    ASJC Scopus subject areas

    • Energy Engineering and Power Technology
    • Nuclear Energy and Engineering

    Cite this

    Tasaki, Y., & Yamaji, A. (2018). Preliminary core and fuel design of bwr with multi-Axial fuel shuffling. In Proceedings of the 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018 (pp. 1144-1152). American Nuclear Society.

    Preliminary core and fuel design of bwr with multi-Axial fuel shuffling. / Tasaki, Yudai; Yamaji, Akifumi.

    Proceedings of the 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018. American Nuclear Society, 2018. p. 1144-1152.

    Research output: Chapter in Book/Report/Conference proceedingConference contribution

    Tasaki, Y & Yamaji, A 2018, Preliminary core and fuel design of bwr with multi-Axial fuel shuffling. in Proceedings of the 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018. American Nuclear Society, pp. 1144-1152, 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018, Charlotte, United States, 18/4/8.
    Tasaki Y, Yamaji A. Preliminary core and fuel design of bwr with multi-Axial fuel shuffling. In Proceedings of the 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018. American Nuclear Society. 2018. p. 1144-1152
    Tasaki, Yudai ; Yamaji, Akifumi. / Preliminary core and fuel design of bwr with multi-Axial fuel shuffling. Proceedings of the 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018. American Nuclear Society, 2018. pp. 1144-1152
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