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pellet in molten Zr claddingIto, Ayumi*; Yamashita, Susumu; Tasaki, Yudai; Kakiuchi, Kazuo; Kobayashi, Yoshinao*
Journal of Nuclear Science and Technology, 60(4), p.450 - 459, 2023/04
Times Cited Count：0 Percentile：0.01(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.
Onozawa, Atsushi; Kushida, Teruo; Kanazawa, Hiroyuki
JAERI-Tech 2004-061, 39 Pages, 2004/11
JAERI-Tech-2004-061.pdf:8.64MB
The swelling observed on irradiated fuels is caused by the accumulation of fission products and irradiation defects. The swelling ratio is changed along with radius region in the pellet due to burn up difference caused by that of neutron flux. To investigate the swelling behavior at the small area of the pellet, it is needed to measure the density of fuel fragments picked from an irradiated pellet. In this circumstance, once-through type densitometer was developed to measure the density of the small irradiated specimen precisely and to handle the samples easily with remote control systems. Several kinds of metallic and ceramic standard specimens are prepared to investigate the dependence of the sample weight, density and porosity on the accuracy. The results of characteristic examination using these specimens indicate that this densitometer has enough accuracy. In addition, some parts of this apparatus are controlled by motor drive units, which made it possible to measure the density full-automatically.
Nakamura, Jinichi; Sugiyama, Tomoyuki; Nakamura, Takehiko; Kanazawa, Toru; Sasajima, Hideo
JAERI-Tech 2003-008, 32 Pages, 2003/03
JAERI-Tech-2003-008.pdf:1.49MB
no abstracts in English
Ando, Yoshihira*; Nishihara, Kenji; Takano, Hideki
Journal of Nuclear Science and Technology, 37(10), p.924 - 933, 2000/10
no abstracts in English
fuel discsUne, Katsumi*; Nogita, Kazuhiro*; Shiratori, Tetsuo; Hayashi, Kimio
Journal of Nuclear Materials, 288(1), p.20 - 28, 2000/09
Times Cited Count：19 Percentile：77.96(Materials Science, Multidisciplinary)no abstracts in English
fuel under reactivity initiated accident conditionsSasajima, Hideo; Nakamura, Jinichi; Fuketa, Toyoshi; Uetsuka, Hiroshi
Journal of Nuclear Science and Technology, 36(11), p.1101 - 1104, 1999/11
Times Cited Count：2 Percentile：21.18(Nuclear Science & Technology)no abstracts in English
Yanagisawa, Kazuaki; Omichi, Toshihiko*; Shirasu, Noriko; Muromura, Tadasumi; *
JAERI-Tech 99-032, 65 Pages, 1999/03
no abstracts in English
pelletNakamura, Jinichi; Uchida, Masaaki; Uetsuka, Hiroshi; Furuta, Teruo
IAEA-TECDOC-1036, 0, p.127 - 138, 1998/08
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
pelletNakamura, Jinichi; Uchida, Masaaki; Uetsuka, Hiroshi; Kodaira, Tsuneo; Yamahara, Takeshi;
Proc. of Int. Topical Meeting on LWR Fuel Performance, 0, p.499 - 506, 1997/03
no abstracts in English
latticesNakajima, Ken;
Nuclear Technology, 113, p.375 - 379, 1996/03
Times Cited Count：5 Percentile：45.11(Nuclear Science & Technology)no abstracts in English
pellet irradiated at HBWRNakamura, Jinichi; Furuta, Teruo; Sukegawa, T
HPR-347, 12 Pages, 1996/00
no abstracts in English
Nakamura, Jinichi; Uetsuka, Hiroshi; Kono, Nobuaki; ; ; Furuta, Teruo
HPR-345 (Vol. II), 0, 13 Pages, 1995/00
no abstracts in English
fuel particlesMinato, Kazuo; Ogawa, Toru; Fukuda, Kosaku; ; ;
Journal of Nuclear Materials, 208, p.266 - 281, 1994/00
Times Cited Count：43 Percentile：94.61(Materials Science, Multidisciplinary)no abstracts in English
Ogawa, Toru; Minato, Kazuo; Fukuda, Kosaku; ; ; Sekino, Hajime; ; Ito, Tadaharu; ;
Nuclear Technology, 96, p.314 - 322, 1991/12
Times Cited Count：12 Percentile：76.66(Nuclear Science & Technology)no abstracts in English
O
doped UO fuel in reactivity initiated accident conditionsYanagisawa, Kazuaki
Journal of Nuclear Science and Technology, 28(5), p.459 - 471, 1991/05
no abstracts in English
fuel under reactivity initiated accident conditionsYanagisawa, Kazuaki; Mimura, Hideaki; Kimura, Yasuhiko
JAERI-M 90-164, 64 Pages, 1990/09
no abstracts in English
Yanagisawa, Kazuaki
JAERI-M 90-120, 320 Pages, 1990/08
no abstracts in English
kernel and pyrocarbon layer of BISO-coated fuel particles at extremely high temperaturesHayashi, Kimio; Fukuda, Kosaku
Journal of Nuclear Materials, 174, p.35 - 44, 1990/00
Times Cited Count：1 Percentile：19.6(Materials Science, Multidisciplinary)no abstracts in English
