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Mohamad, A. B.; Udagawa, Yutaka
Nuclear Technology, 210(2), p.245 - 260, 2024/02
Times Cited Count：1 Percentile：72.91(Nuclear Science & Technology)Taniguchi, Yoshinori; Mihara, Takeshi; Kakiuchi, Kazuo; Udagawa, Yutaka
Annals of Nuclear Energy, 195, p.110144_1 - 110144_11, 2024/01
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)Shaimerdenov, A.*; Gizatulin, S.*; Dyussambayev, D.*; Askerbekov, S.*; Ueta, Shohei; Aihara, Jun; Shibata, Taiju; Sakaba, Nariaki
Nuclear Engineering and Technology, 54(8), p.2792 - 2800, 2022/08
Times Cited Count：7 Percentile：88.9(Nuclear Science & Technology)Udagawa, Yutaka; Tasaki, Yudai
JAEA-Data/Code 2021-007, 56 Pages, 2021/07
JAEA-Data-Code-2021-007.pdf:5.05MB
Japan Atomic Energy Agency (JAEA) has released FEMAXI-8 in 2019 as the latest version of the fuel performance code FEMAXI, which has been developed to analyze thermal and mechanical behaviors of a single fuel rod in mainly normal operation conditions and anticipated transient conditions. This report summarizes a newly developed model to analyze intragranular fission gas behaviors considering size distribution of gas bubbles and their dynamics. While the intragranular fission gas behavior models implemented in the previous FEMAXI versions have supported only treating single bubble size for a given fuel element, the new model supports multiple gas groups according to their size and treats their dynamic behaviors, making the code more versatile. The model was first implemented as a general module that takes arbitrary number of bubble groups and spatial mesh division for a given fuel grain system. An interface module to connect the model to FEMAXI-8 was then developed so that it works as a 2 bubble groups model, which is the minimum configuration of the multi-grouped model to be operated with FEMAXI-8 at the minimum calculation cost. FEMAXI-8 with the new intragranular model was subjected to a systematic validation calculation against 144 irradiation test cases and recommended values for model parameters were determined so that the code makes reasonable predictions in terms of fuel center temperature, fission gas release, etc. under steady-state and power ramp conditions.
Udagawa, Yutaka; Yamauchi, Akihiro*; Kitano, Koji*; Amaya, Masaki
JAEA-Data/Code 2018-016, 79 Pages, 2019/01
JAEA-Data-Code-2018-016.pdf:2.75MB
FEMAXI-8 is the latest version of the fuel performance code FEMAXI developed by JAEA. A systematic validation work has been achieved against 144 irradiation test cases, after many efforts have been made, in development of new models, improvements in existing models and the code structure, bug-fixes, construction of irradiation-tests database and other infrastructures.
Nakata, Tetsuo*; Katanishi, Shoji; Takada, Shoji; Yan, X.; Kunitomi, Kazuhiko
Nihon Genshiryoku Gakkai Wabun Rombunshi, 2(4), p.478 - 489, 2003/12
no abstracts in English
Suzuki, Motoe; Saito, Hioraki*
JAERI-Data/Code 97-046, 210 Pages, 1997/11
JAERI-Data-Code-97-046.pdf:5.41MB
no abstracts in English
Yanagisawa, Kazuaki;
Proc. of the 4th Int. Symp. on Advanced Nuclear Energy Research (JAERI-CONF 1/JAERI-M 92-207), p.509 - 516, 1992/12
no abstracts in English
; Suzuki, Kunihiro; Hino, Ryutaro; Takase, Kazuyuki; Inagaki, Yoshiyuki; Ioka, Ikuo
Nucl. Eng. Des., 120, p.435 - 445, 1990/00
Times Cited Count：3 Percentile：40.4(Nuclear Science & Technology)no abstracts in English
Kawamura, Hiroshi;
Journal of Nuclear Science and Technology, 24(12), p.1045 - 1054, 1987/12
Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)no abstracts in English
C;
Nucl.Eng.Des., 92, p.15 - 26, 1986/00
Times Cited Count：6 Percentile：59.04(Nuclear Science & Technology)no abstracts in English
Mohamad, A. B.; Udagawa, Yutaka; Nemoto, Yoshiyuki; Yamashita, Shinichiro
no journal, ,
