Benchmark of fuel performance codes for fecral cladding behavior analysis

G. Pastore, K. A. Gamble, M. Cherubini, C. Giovedi, A. Marino, A. Yamaji, Y. Kaji, P. van Uffelen, M. S. Veshchunov

研究成果: Paper査読

抄録

Oxidation-resistant iron-chromium-aluminum (FeCrAl) steels have been proposed for application as cladding materials in light water reactor fuel rods with improved accident tolerance. Within the Coordinated Research Project ACTOF of the International Atomic Energy Agency (IAEA), a fuel performance modeling benchmark for FeCrAl cladding behavior was conducted. During this effort, calculations were performed with various fuel performance codes for a set of fuel rod problems with FeCrAl steel as cladding material, and results were compared to each other. Comparisons to Zircaloy-4 cladding behavior under the same conditions were also included. Considered cases covered both normal operating and loss of coolant conditions. Participating organizations were INL (BISON code), NINE (TRANSURANUS), JAEA in cooperation with Waseda University (FEMAXI-7), University of São Paulo (FRAPCON) and CNEA (BACO). Results of the benchmark are presented and discussed in this contribution.

本文言語English
ページ1038-1047
ページ数10
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
国/地域United States
CitySeattle
Period19/9/2219/9/27

ASJC Scopus subject areas

  • 燃料技術
  • 原子力エネルギーおよび原子力工学

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