Analysis of fecral-Ods cladded fuel performance during BWR power ramp with Femaxi-7

Yoshihiro Fujiwara, Akifumi Yamaji, Shigeharu Ukai, Kan Sakamoto, Shinichiro Yamashita

研究成果: Paper査読

抄録

In Japan, as one of the candidates for the accident tolerant fuel cladding, Oxide Dispersion Strengthened (ODS) type of FeCrAl (FeCrAl-ODS) steel is being developed for BWR. Compared with Zircaloy (Zry), it has higher thermal expansion rate and is expected to have lower irradiation creep rate and higher yield stress. The purpose of this study is to perform FEMAXI-7 analyses of FeCrAl-ODS cladded fuel rod under BWR power ramp test conditions to reveal influence of such cladding properties on PCMI behavior. Sensitivity analyses have been conducted with different cladding creep and plastic deformation models / parameters. The evaluated range of pellet temperature and PCMI contact pressure of FeCrAl-ODS cladded fuel rod is comparable or less than those with Zry cladded fuel rod. Hence, the results indicate that the current evaluations with FEMAXI-7 is well within the experience of the code with typical light water reactor fuel pellet modeling with respect to evaluations of stress-strain interactions between pellet and cladding. More investigations may be necessary as the irradiation data are gained with FeCrAl-ODS and incorporated into mechanical models of the cladding.

本文言語English
ページ494-502
ページ数9
出版ステータスPublished - 2020
イベント14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019 - Seattle, United States
継続期間: 2019 9 222019 9 27

Conference

Conference14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019
CountryUnited States
CitySeattle
Period19/9/2219/9/27

ASJC Scopus subject areas

  • Fuel Technology
  • Nuclear Energy and Engineering

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