Effects of fuel temperature history approximations on neutronics properties of a BWR assembly

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

    Abstract

    We study the effects of fuel temperature approximation made in the history part of group constant generation for a boiling water reactor (BWR) assembly. We compare produced nuclide densities and group constants when the burnup calculation in the history part uses either realistic fuel temperatures provided by a fuel performance code or an effective flat and constant fuel temperature. The results mirror our previous findings for PWR assemblies: The fuel temperature approximation has a noticeable effect on gadolinium burnout and production of fissile actinides. Differences in the actinide content of the assembly are further reflected into homogenized absorption and fission cross sections at high burnups.
    Original languageEnglish
    Title of host publicationProceedings of the PHYSOR 2018, Cancun, Mexico
    PublisherAmerican Nuclear Society ANS
    Pages2215-2226
    Number of pages12
    Publication statusPublished - 2018
    MoE publication typeNot Eligible
    EventPHYSOR 2018: Reactor Physics Paving The Way Towards More Efficient Systems - Cancun, Mexico
    Duration: 22 Apr 201826 Apr 2018

    Conference

    ConferencePHYSOR 2018
    Abbreviated titlePHYSOR 2018
    CountryMexico
    CityCancun
    Period22/04/1826/04/18

    Fingerprint Dive into the research topics of 'Effects of fuel temperature history approximations on neutronics properties of a BWR assembly'. Together they form a unique fingerprint.

  • Cite this

    Valtavirta, V., & Leppänen, J. (2018). Effects of fuel temperature history approximations on neutronics properties of a BWR assembly. In Proceedings of the PHYSOR 2018, Cancun, Mexico (pp. 2215-2226). American Nuclear Society ANS.