Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
random mediaAraki, Shohei; Yamane, Yuichi; Ueki, Taro; Tonoike, Kotaro
Nuclear Science and Engineering, 195(10), p.1107 - 1117, 2021/10
Times Cited Count：2 Percentile：30.55(Nuclear Science & Technology)Criticality control of random media such as fuel debris is one of the most important safety issues in post-accident management. 
spectrum randomizing model is expected to simulate such random media because it is well known that the noise can describe a diverse range of random and disordered natural phenomena. In this paper, we focused on the relationship between the multiplication factor and moderation condition in the random media. A number of random media were realized with the spectrum randomizing model that is based on the Randomized Weierstrass function (RWF). The volume ratio of concrete to fuel was adopted as an index for the moderation condition. The multiplication factors were calculated with a two-energy group Monte Carlo calculation. The calculation results were analyzed by using variance, skewness, and kurtosis. Those statistical parameters had an extreme value around the optimum moderation condition. This result suggested that it is possible to predict the rough trend of variation range, distortion, and outlier of multiplication factors in the random media.
on effective multiplication factor in 1/f
spectrum random systemAraki, Shohei; Yamane, Yuichi; Ueki, Taro; Tonoike, Kotaro
Proceedings of International Conference on the Physics of Reactors; Transition To A Scalable Nuclear Future (PHYSOR 2020) (USB Flash Drive), 8 Pages, 2020/03
We investigated the dependence of the effective multiplication factor (k
) in the 1/f noise model. We conducted the two-group Monte Carlo calculations. We found that the standard deviation of the k distribution showed the positive correlation with the value because the spatial distribution of the fuel became less uniform as the value increased.
Reactor Integral Test Working Group, JENDL Committee
JAEA-Data/Code 2017-006, 152 Pages, 2017/05
JAEA-Data-Code-2017-006.pdf:13.46MBJAEA-Data-Code-2017-006(errata).pdf:0.07MB
JAEA-Data-Code-2017-006-appendix1(CD-ROM).zip:115.88MBJAEA-Data-Code-2017-006-appendix2(CD-ROM).zip:110.88MB
A benchmark database which is devoted to the evaluation of the future JENDL against the criticality of light water reactors was prepared, where the ICSBEP and IRPhEP handbooks by OECD/NEA were utilized effectively. Specific features of this report can be described as follows: (1) The recommendation for benchmarking is based on careful reviewing for the document and related information. Validity of the original benchmark evaluation is carefully checked, and numerical results obtained with JENDL-4.0 are considered. (2) Heterogeneity effect of PuO
particles dispersed in fuel medium is consistently quantified for the MOX fuel-loaded experimental data. This precise evaluation is realized by the newly developed finite fuel pin bundle model with the Monte Carlo neutron transport code. (3) Sensitivity analysis is conducted in order to specify nuclear data whose difference between recent nuclear data libraries significantly affects the critical parameter calculation.
Sasa, Toshinobu; Tsujimoto, Kazufumi; Kaneko, Kunio*; Takano, Hideki
Journal of Nuclear Science and Technology, 39(Suppl.2), p.1183 - 1186, 2002/08
no abstracts in English
Yamamoto, Toshihiro; Nakamura, Takemi*; Miyoshi, Yoshinori
JAERI-Data/Code 2001-001, 30 Pages, 2001/02
JAERI-Data-Code-2001-001.pdf:1.53MB
no abstracts in English
Yamamoto, Toshihiro; Nakamura, Takemi*; Miyoshi, Yoshinori
Journal of Nuclear Science and Technology, 37(1), p.41 - 52, 2000/01
no abstracts in English
Yamamoto, Toshihiro; Sakurai, Kiyoshi; *
Annals of Nuclear Energy, 25(9), p.599 - 607, 1998/00
Times Cited Count：1 Percentile：15.02(Nuclear Science & Technology)no abstracts in English
Nojiri, Naoki; Yamashita, Kiyonobu; Fujimoto, Nozomu; Nakano, Masaaki*; Yamane, Tsuyoshi; Akino, Fujiyoshi
JAERI-Tech 97-060, 34 Pages, 1997/11
no abstracts in English
Miyoshi, Yoshinori; ; Tonoike, Kotaro; Izawa, Naoki; Sugikawa, Susumu; Okazaki, Shuji
Nuclear Technology, 118(1), p.69 - 82, 1997/04
Times Cited Count：13 Percentile：70.31(Nuclear Science & Technology)no abstracts in English
; Takano, Hideki; ; A.G.Morozov*; V.S.Smirnov*; V.V.Orlov*
Proc. of ARS94 Int. Topical Meeting on Advanced Reactors Safety,Vol. 1, 0, p.544 - 548, 1994/00
no abstracts in English
Yamamoto, Toshihiro; *
JAERI-M 93-218, 18 Pages, 1993/11
no abstracts in English
; C.A.Brebbia*
Boundary Elements XIV, Vol.1; Field Problems and Applications, p.25 - 38, 1992/00
no abstracts in English
; C.A.Brebbia*
Engineering Analysis with Boundary Elements, 8(5), p.239 - 244, 1991/10
Times Cited Count：9 Percentile：76.25(Engineering, Multidisciplinary)no abstracts in English
Robutsuri No Kenkyu, (36), p.10 - 14, 1987/00
no abstracts in English
; Shimooke, Takanori
Nihon Genshiryoku Gakkai-Shi, 27(6), p.540 - 552, 1985/00
Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)no abstracts in English
*; ;
JAERI-M 9638, 75 Pages, 1981/08
no abstracts in English
; Tasaka, Kanji
JAERI-M 4588, 47 Pages, 1971/09
no abstracts in English
frequency spectrumAraki, Shohei; Yamane, Yuichi; Ueki, Taro; Tonoike, Kotaro
no journal, ,
We investigated the effect of the degree of randomness on the distribution of neutron multiplication factors (
) calculated for fuel debris for the purpose of criticality risk assessment. The calculation results with the model randomized with frequency spectrum showed a positive correlation between the exponent and variance of the () distribution.
Ikeda, Reiji*; Ho, H. Q.; Fujimoto, Nozomu*; Hamamoto, Shimpei; Nagasumi, Satoru; Ishitsuka, Etsuo
no journal, ,
no abstracts in English
