Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Fujimoto, Nozomu*; Fukuda, Kodai*; Honda, Yuki*; Tochio, Daisuke; Ho, H. Q.; Nagasumi, Satoru; Ishii, Toshiaki; Hamamoto, Shimpei; Nakano, Yumi*; Ishitsuka, Etsuo
JAEA-Technology 2021-008, 23 Pages, 2021/06
JAEA-Technology-2021-008.pdf:2.62MB
The effect of mesh division around the burnable poison rod on the burnup calculation of the HTTR core was investigated using the SRAC code system. As a result, the mesh division inside the burnable poison rod does not have a large effect on the burnup calculation, and the effective multiplication factor is closer to the measured value than the conventional calculation by dividing the graphite region around the burnable poison rod into a mesh. It became clear that the mesh division of the graphite region around the burnable poison rod is important for more appropriately evaluating the burnup behavior of the HTTR core..
Ishitsuka, Etsuo; Nakashima, Koki*; Nakagawa, Naoki*; Ho, H. Q.; Ishii, Toshiaki; Hamamoto, Shimpei; Takamatsu, Kuniyoshi; Kenzhina, I.*; Chikhray, Y.*; Matsuura, Hideaki*; et al.
JAEA-Technology 2020-008, 16 Pages, 2020/08
JAEA-Technology-2020-008.pdf:2.98MB
As a summer holiday practical training 2019, the feasibility study for nuclear design of a nuclear battery using HTTR core was carried out, and the 
U enrichment and burnable poison of the fuel, which enables continuous operation for 30 years with thermal power of 5 MW, were studied by the MVP-BURN. As a result, it is clear that a fuel with U enrichment of 12%, radius of burnable poison and natural boron concentration of 1.5 cm and 2wt% are required. As a next step, the downsizing of core will be studied.
Kojima, Kensuke
Proceedings of International Conference on the Physics of Reactors; Unifying Theory and Experiments in the 21st Century (PHYSOR 2016) (USB Flash Drive), p.3283 - 3292, 2016/05
The MOSRA system has been developing to improve the applicability of the neutronic characteristic analyses. The cell calculation module MOSRA-SRAC is a core module of MOSRA, and applicability tests for realistic problems are required. As a test, MOSRA-SRAC is validated by comparison with measured values. As the measurement, the post irradiation examination SFCOMPO 99-5 is chosen. In the examination, the compositions of major heavy metal and fission product nuclides in a UO
-GdO
fuel rod pulled from the 8
8 BWR fuel assembly used in TEPCO's Fukushima-Daini-2 were measured. The result shows good agreement between calculated and measured value. For uranium and plutonium nuclides, calculated values agree within 5% except for 
Pu. Pu composition is overestimated by 30%, and the overestimation is caused by the unclearness of the void faction history of the fuel rod. For fission products, calculated values agree within approximately 10%.
Fujimoto, Nozomu; Nojiri, Naoki; Ando, Hiroei*; Yamashita, Kiyonobu*
Nuclear Engineering and Design, 233(1-3), p.23 - 36, 2004/10
Times Cited Count：13 Percentile：63.95(Nuclear Science & Technology)In the nuclear design of the HTTR, the reactivity balance is planned so that the design requirements are fully satisfied. Moreover, the reactivity coefficients are evaluated to confirm the safety characteristics of the reactor. The power distribution in the core was optimized by changing the uranium enrichment to maintain the fuel temperature at less than the limit (1600
C). Deviation from the optimized distribution due to the burnup of fissile materials was avoided by flattening time-dependent changes in local reactivities. Flattening was achieved by optimizing the specifications of the burnable poisons. The original nuclear design model had to be modified based on the first critical experiments. The Monte Carlo code MVP was also used to predict criticality of the initial core. The predicted excess reactivities are now in good agreement with the experimental results.
Fujimoto, Nozomu; Nojiri, Naoki; Yamashita, Kiyonobu*
Nuclear Engineering and Design, 233(1-3), p.155 - 162, 2004/10
Times Cited Count：2 Percentile：17.18(Nuclear Science & Technology)The HTTR uses low-enriched uranium fuel with burnable poison rod. For validation of the nuclear design code system for the HTTR, a critical assembly of VHTRC had been constructed. The calculation uncertainties of effective multiplication factor, neutron flux distribution, burnable poison reactivity worth, and control rod worth, temperature coefficients were evaluated. Calculation accuracy of a Monte Carlo code is also evaluated.
Fujimoto, Nozomu; Yamashita, Kiyonobu
JAERI-Research 99-059, p.43 - 0, 1999/11
JAERI-Research-99-059.pdf:2.51MB
no abstracts in English
Fujimoto, Nozomu; U.Ohlig*; H.Brockmann*; Yamashita, Kiyonobu
JAERI-Tech 98-060, 56 Pages, 1999/01
no abstracts in English
Kugo, Teruhiko; Shimada, Shoichiro*; Okubo, Tsutomu; Ochiai, Masaaki
JAERI-Research 98-059, 40 Pages, 1998/10
JAERI-Research-98-059.pdf:1.73MB
no abstracts in English
Fujimoto, Nozomu; Nojiri, Naoki; Nakano, Masaaki*; Takeuchi, Mitsuo; Fujisaki, Shingo; Yamashita, Kiyonobu
JAERI-Tech 98-021, 66 Pages, 1998/06
no abstracts in English
Akino, Fujiyoshi; Yamane, Tsuyoshi
Nihon Genshiryoku Gakkai-Shi, 40(4), p.262 - 264, 1998/00
no abstracts in English
Yamashita, Kiyonobu; Shindo, Ryuichi; Murata, Isao; Maruyama, So; Fujimoto, Nozomu; Takeda, Takeshi
Nuclear Science and Engineering, 122, p.212 - 228, 1996/00
Times Cited Count：23 Percentile：85.72(Nuclear Science & Technology)no abstracts in English
Yamashita, Kiyonobu
Journal of Nuclear Science and Technology, 31(9), p.979 - 985, 1994/09
Times Cited Count：6 Percentile：52.28(Nuclear Science & Technology)no abstracts in English
Yamashita, Kiyonobu; Shindo, Ryuichi; Murata, Isao
The Safety,Status and Future of Non-Commercial Reactors and Irradiation Facilities,Vol. 1, p.350 - 358, 1990/09
no abstracts in English
Yamashita, Kiyonobu; Shindo, Ryuichi; Murata, Isao; Maruyama, So; *
JAERI-M 89-118, 67 Pages, 1989/09
no abstracts in English
*;
JAERI-M 84-230, 34 Pages, 1984/12
no abstracts in English
Akino, Fujiyoshi
JAERI-M 82-207, 180 Pages, 1982/12
no abstracts in English
; *; ;
JAERI-M 9956, 23 Pages, 1982/03
no abstracts in English
Akino, Fujiyoshi; ; ; ;
JAERI-M 9223, 21 Pages, 1980/11
no abstracts in English
JAERI-M 8847, 17 Pages, 1980/05
no abstracts in English
; ; ; ; ; ; ; Suzuki, Katsuo; ;
JAERI-M 8399, 253 Pages, 1979/08
no abstracts in English
; *; *; *
JAERI-M 7350, 64 Pages, 1977/10
no abstracts in English
