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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
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.
Inaba, Yoshitomo; Nishihara, Tetsuo
Annals of Nuclear Energy, 101, p.383 - 389, 2017/03
Times Cited Count:7 Percentile:56.46(Nuclear Science & Technology)In order to ensure the thermal integrity of fuel in High Temperature Gas-cooled Reactors (HTGRs), it is necessary that the maximum fuel temperature in normal operation is to be lower than a thermal design target. In the core thermal-hydraulic design of block-type HTGRs, the maximum fuel temperature should be evaluated considering data such as thermal power, core geometry, power density and neutron fluence distributions, and core coolant flow distribution. The fuel temperature calculation code used in the design stage of the High Temperature engineering Test Reactor (HTTR) presupposes to run on UNIX systems, and its operation and execution procedure are complicated and are not user-friendly. Therefore, a new fuel temperature calculation code named FTCC which has a user-friendly system such as a simple and easy operation and execution procedure, was developed. This paper describes calculation objects and models, basic equations, improvement points from the HTTR design code in FTCC, and the result of a validation calculation with FTCC. The calculation result obtained by FTCC provides good agreement with that of the HTTR design code, and then FTCC will be used as one of the design codes for HTGRs. In addition, the effect of cooling forms on the maximum fuel temperature is investigated by using FTCC. As a result, it was found that the effect of center hole cooling for hollow fuel compacts and gapless cooling with monolithic type fuel rods on reducing the temperature is very high.
Tobita, Masahiro*; Matsui, Yoshinori
JAERI-Tech 2003-042, 132 Pages, 2003/03
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.
Hayashi, Takafumi*; Suyama, Kenya; Mochizuki, Hiroki*; Nomura, Yasushi
JAERI-Tech 2001-041, 158 Pages, 2001/06
no abstracts in English
Fujimoto, Nozomu; Nojiri, Naoki; Takada, Eiji*; Saito, Kenji; Kobayashi, Shoichi; Sawahata, Hiroaki; Kokusen, Shigeru
JAERI-Tech 2000-091, 49 Pages, 2001/03
no abstracts in English
*; Kaji, Yoshiyuki; *; ; *; Kaburaki, Hideo
Keisan Kogaku Koenkai Rombunshu, 3(1), p.59 - 62, 1998/05
no abstracts in English
Yamane, Tsuyoshi; Akino, Fujiyoshi;
PHYSOR 96: Int. Conf. on the Physics of Reactors, 2, p.E290 - E299, 1996/00
no abstracts in English
; Yamane, Tsuyoshi
JAERI-Research 95-081, 32 Pages, 1995/11
no abstracts in English
; Yamane, Tsuyoshi; Sasa, Toshinobu
JAERI-Data/Code 94-013, 17 Pages, 1994/10
no abstracts in English
Fujimoto, Nozomu; Maruyama, So; Sudo, Yukio
JAERI-M 89-049, 53 Pages, 1989/05
no abstracts in English
Takamura, Saburo; ; *; *
Journal of Physics; Condensed Matter, 1, p.4527 - 4533, 1989/00
Times Cited Count:3 Percentile:23.72(Physics, Condensed Matter)no abstracts in English
Arigane, Kenji
JAERI-M 87-063, 133 Pages, 1987/04
no abstracts in English
*; *; ; *; *
JAERI-M 86-084, 32 Pages, 1986/06
no abstracts in English
; *
Journal of Nuclear Science and Technology, 23(2), p.151 - 159, 1986/00
Times Cited Count:5 Percentile:54.53(Nuclear Science & Technology)no abstracts in English
Nihon Genshiryoku Gakkai-Shi, 20(11), p.829 - 834, 1978/00
Times Cited Count:0no abstracts in English
Nucl.Eng.Des., 31(1), p.66 - 71, 1974/01
Times Cited Count:5no abstracts in English