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Ikeda, Reiji*; Ho, H. Q.; Nagasumi, Satoru; Ishii, Toshiaki; Hamamoto, Shimpei; Nakano, Yumi*; Ishitsuka, Etsuo; Fujimoto, Nozomu*
JAEA-Technology 2021-015, 32 Pages, 2021/09
JAEA-Technology-2021-015.pdf:2.74MB
Burnup calculation of the HTTR considering temperature distribution and detailed burning regions was carried out using MVP-BURN code. The results show that the difference in k
, as well as the difference in average density of some main isotopes, is insignificant between the cases of uniform temperature and detailed temperature distribution. However, the difference in local density is noticeable, being 6% and 8% for 
U and 
Pu, respectively, and even 30% for the burnable poison 
B. Regarding the division of burning regions to more detail, the change of k is also small of 0.6%
k/k or less. The small burning region gives a detailed distribution of isotopes such as U, Pu, and B. As a result, the effect of graphite reflector and the burnup behavior could be evaluated more clearly compared with the previous study.
Ishikawa, Hirotaku*; Kai, Tetsuya; Sato, Hirotaka*; Kamiyama, Takashi*
Journal of Nuclear Science and Technology, 56(2), p.221 - 227, 2019/02
Times Cited Count：4 Percentile：35.14(Nuclear Science & Technology)Narukawa, Takafumi; Amaya, Masaki
Journal of Nuclear Science and Technology, 53(11), p.1758 - 1765, 2016/11
Times Cited Count：10 Percentile：64.55(Nuclear Science & Technology)Tobita, Masahiro*; Matsui, Yoshinori
JAERI-Tech 2003-042, 132 Pages, 2003/03
JAERI-Tech-2003-042.pdf:7.19MB
Prediction of irradiation temperature is one of the important issues in the design of the capsule for irradiation test. Many kinds of capsules with complex structure have been designed for recent irradiation requests, and three-dimensional (3D) temperature calculation becomes inevitable for the evaluation of irradiation temperature. For such 3D calculation, however, many works are usually needed for input data preparation, and a lot of time and resources are necessary for parametric studies in the design. To improve such situation, JAERI introduced 3D-FEM (finite element method) code NISA (Numerically Integrated elements for System Analysis) and developed several subprograms, which enabled to support input preparation works in the capsule design. The 3D temperature calculation of the capsule are able to carried out in much easier way by the help of the subprograms, and specific features in the irradiation tests such as non-uniform gamma heating in the capsule, becomes to be considered.
Tobita, Masahiro*; Matsui, Yoshinori
KAERI/GP-195/2002, p.87 - 95, 2002/00
In the Japan Materials Testing Reactor (JMTR) of Japan Atomic Energy Research Institute (JAERI), the temperature distribution inside of irradiation specimens and capsules structure material are evaluated in the design of irradiation capsules. For the evaluation of detailed temperature distribution, NISA (Numerically Integrated elements for System Analysis) code has been introduced, and subprograms are developed to simplify the input data of the capsules structure and the analysis conditions using the three-dimensional finite element method. By the development of subprograms, prediction of the temperature distribution inside of irradiation specimens and capsules structure material became detailed and more accurate than calculation by one-dimensional code. Also estimation of detail temperature distribution during irradiation became possible based on the indication of thermocouple.
Nihira, Takeshi*; Iwata, Tadao*; Iwase, Akihiro
JAERI-Research 2001-045, 33 Pages, 2001/11
JAERI-Research-2001-045.pdf:1.27MB
no abstracts in English
Takase, Kazuyuki; Kunugi, Tomoaki; ; Seki, Yasushi
Fusion Engineering and Design, 42, p.83 - 88, 1998/00
Times Cited Count：13 Percentile：70.38(Nuclear Science & Technology)no abstracts in English
Kunii, Katsuhiko; Iwamura, Takamichi; Murao, Yoshio
Journal of Nuclear Science and Technology, 34(1), p.21 - 29, 1997/01
Times Cited Count：1 Percentile：14.48(Nuclear Science & Technology)no abstracts in English
Takase, Kazuyuki; Kunugi, Tomoaki; Seki, Yasushi
Proc. of Int. Topical Meetig on Advanced Reactors Safety, 2, p.1268 - 1275, 1997/00
no abstracts in English
Ioka, Ikuo; Inagaki, Yoshiyuki; Suzuki, Kunihiro; Kunitomi, Kazuhiko;
Nihon Genshiryoku Gakkai-Shi, 37(3), p.217 - 227, 1995/00
Times Cited Count：1 Percentile：17.33(Nuclear Science & Technology)no abstracts in English
Kunii, Katsuhiko; Iwamura, Takamichi; Murao, Yoshio
Prog. Nucl. Energy, 29(SUPPL), p.405 - 412, 1995/00
no abstracts in English
Murata, Isao; Yamashita, Kiyonobu; Maruyama, So; Shindo, Ryuichi; Fujimoto, Nozomu; Sudo, Yukio; Nakata, Tetsuo*
Journal of Nuclear Science and Technology, 31(1), p.62 - 72, 1994/01
Times Cited Count：4 Percentile：42.03(Nuclear Science & Technology)no abstracts in English
; Kumamaru, Hiroshige; Murata, Hideo; Anoda, Yoshinari; Kukita, Yutaka
JAERI-M 93-200, 56 Pages, 1993/10
no abstracts in English
Harayama, Yasuo; Hoshiya, Taiji; ; Niimi, Motoji; Kobayashi, Toshiki*
Journal of Nuclear Science and Technology, 30(4), p.291 - 301, 1993/04
Times Cited Count：4 Percentile：44.62(Nuclear Science & Technology)no abstracts in English
Nishimura, Akihiko; ; Oba, Hironori; Shibata, Takemasa
Journal of Nuclear Science and Technology, 30(3), p.270 - 273, 1993/03
Times Cited Count：13 Percentile：82.84(Nuclear Science & Technology)no abstracts in English
Harayama, Yasuo; ; Hoshiya, Taiji
Journal of Nuclear Science and Technology, 28(10), p.961 - 964, 1991/10
no abstracts in English
Maruyama, So; Yamashita, Kiyonobu; Fujimoto, Nozomu; Murata, Isao; Shindo, Ryuichi; Sudo, Yukio
The Safety,Status and Future of Non-Commercial Reactors and Irradiation Facilities,Vol. 1, p.304 - 311, 1990/09
no abstracts in English
;
Nuclear Technology, 78(9), p.207 - 215, 1987/09
no abstracts in English
Arigane, Kenji
JAERI-M 87-063, 133 Pages, 1987/04
no abstracts in English
; ; ; ; ;
Nihon Genshiryoku Gakkai-Shi, 29(2), p.133 - 140, 1987/02
Times Cited Count：1 Percentile：19.15(Nuclear Science & Technology)no abstracts in English
