TY - CONF
T1 - Analysis of fecral-Ods cladded fuel performance during BWR power ramp with Femaxi-7
AU - Fujiwara, Yoshihiro
AU - Yamaji, Akifumi
AU - Ukai, Shigeharu
AU - Sakamoto, Kan
AU - Yamashita, Shinichiro
N1 - Funding Information:
This study is the result of “Development of Technical Basis for Introducing Advanced Fuels Contributing to Safety Improvement of Current Light Water Reactors” carried out under the Project on Development of Technical Basis for Safety Improvement at Nuclear Power Plants by Ministry of Economy, Trade and Industry (METI) of Japan. Part of this work was conducted under “Understanding Mechanisms of Severe Accidents and Improving Safety of Nuclear Reactors by Computer Science” of Institute for Advanced Theoretical and Experimental Physics and Waseda Research Institute for Science and Engineering. Part of this work was supported by Institute for Advanced Theoretical and Experimental Physics, Waseda University.
Publisher Copyright:
Copyright © GLOBAL 2019 - International Nuclear Fuel Cycle Conference and TOP FUEL 2019 - Light Water Reactor Fuel Performance Conference.All rights reserved.
PY - 2020
Y1 - 2020
N2 - 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.
AB - 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.
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M3 - Paper
AN - SCOPUS:85081080374
SP - 494
EP - 502
T2 - 14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019
Y2 - 22 September 2019 through 27 September 2019
ER -