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Endo, Tomohiro*; Noguchi, Akihiro*; Yamamoto, Akio*; Tada, Kenichi
Transactions of the American Nuclear Society, 124(1), p.184 - 187, 2021/06
This study confirmed that the sensitivity analysis of the alpha-eigenvalue can be carried even for non-neutron multiplication systems such as water-only systems. The preliminary results of nuclear data-induced uncertainties of alpha-eigenvalue were smaller than the differences between numerical and experimental results of alpha-eigenvalue. For further investigation, it is necessary to reconsider the experimental bias and the nuclear data-induced uncertainty in alpha-eigenvalue due to the thermal scattering law data of water.
Nishinaka, Ichiro; Nagame, Yuichiro; Ikezoe, Hiroshi; Tanikawa, Masashi*; Zhao, Y. L.*; Sueki, Keisuke*; Nakahara, Hiromichi
Physical Review C, 70(1), p.014609_1 - 014609_10, 2004/07
Times Cited Count：16 Percentile：66.77(Physics, Nuclear)no abstracts in English
*
JNC TJ9400 2000-007, 46 Pages, 2000/03
JNC-TJ9400-2000-007.pdf:2.16MB
For fission cross section and prompt fission neutron spectrum, which largely influence core characteristics of a fast reactor, we have performed experimental and analytical studies for developing an advanced technique to measure absolute fission cross section and neutron fission spectrum for actinide nuclides such as Np237. As the results, we could develop an advanced technique, which combines a normalization technique for the well-known differential cross section and a correction method by a Monte-Carlo code for sample effects. This advanced technique accurately provides both absolute fission cross section and prompt fission neutron spectrum individually. By employing this technique, in this study, we have measured for three actinides (
Np, 
Th and 
U), then, have obtained the fission cross sections and fission spectrum parameter data for those nuclides. Furthermore, we have also performed an analytical study to examine sensitivity of fission spectrum parameter to core multiplication factor by using the standard calculation code for a first reactor.
130 in two mode fissionNishinaka, Ichiro; Nagame, Yuichiro; Tsukada, Kazuaki; Ichikawa, Shinichi; Ikezoe, Hiroshi; Tanikawa, Masashi*; Zhao, Y.*; Sueki, Keisuke*; Nakahara, Hiromichi*
Proceedings of 2nd International Conference on Fission and Neutron-rich Nuclei, p.494 - 496, 2000/03
no abstracts in English
Sakurai, Kiyoshi; Yamamoto, Toshihiro; Arakawa, Takuya*; Naito, Yoshitaka
Journal of Nuclear Science and Technology, 34(6), p.544 - 550, 1997/06
Times Cited Count：2 Percentile：23.01(Nuclear Science & Technology)no abstracts in English
Oigawa, Hiroyuki; Shinohara, Nobuo; Mukaiyama, Takehiko; H.H.Saleh*; T.A.Parish*; W.H.Miller*; S.Raman*
Proc. of 4th Int. Information Exchange Meeting on Actinide and Fission Product Partitioning and Transm, 0, p.341 - 346, 1997/00
no abstracts in English
Yamamoto, Toshihiro; Sakurai, Kiyoshi; Naito, Yoshitaka; Arakawa, Takuya*
Proc. of Topical Meeting on Criticality Safety Challenges in the Next Decade, 0, p.365 - 370, 1997/00
no abstracts in English
; *; *; ;
JAERI-M 84-118, 61 Pages, 1984/07
no abstracts in English
JAERI-M 7356, 112 Pages, 1977/11
no abstracts in English
; ; *
JAERI-M 6993, 51 Pages, 1977/02
no abstracts in English
Journal of Nuclear Science and Technology, 10(12), p.753 - 761, 1973/12
no abstracts in English
;
JAERI-M 4705, 12 Pages, 1972/02
no abstracts in English
/l for the Two Regional Cores of Light Water Moderated UO
and PuO-UO Lattices; *
JAERI-M 4696, 56 Pages, 1972/02
no abstracts in English
; ; ;
JAERI-M 4658, 8 Pages, 1971/12
no abstracts in English
; ; Akino, Fujiyoshi
JAERI-M 4525, 35 Pages, 1971/06
no abstracts in English
Nihon Genshiryoku Gakkai-Shi, 3(9), p.691 - 697, 1961/00
no abstracts in English
Iwamoto, Hiroki; Nishihara, Kenji; Yagi, Takahiro*; Pyeon, C. H.*
no journal, ,
no abstracts in English
Yamane, Yuichi
no journal, ,
In the condition such as erroneous transport of nuclear fuel solution in fuel reprocessing plant, criticality approach in reactor and critical assembly, the retrieval work of fuel debris in FUKUSHIMA DAI-ICHI, and so on, in which an amount of reactivity is inserted into nuclear fuel in a subcritical state, an equation is derived which relates the total reactivity to the asymptotic behavior of the power based on one-point kinetics equation. Existing methods of reactivity measurement needs prompt neutron lifetime, the calculation of which requires the information of the composition and structure of the nuclear fuel. But the new equation doesn't include prompt neutron lifetime. Therefore, it is clearly shown the possibility of reactivity measurement only with neutron counts without the information of inside the nuclear fuel. The power profile calculated by using the new equation shows good agreement with that by using one-point kinetics code.
Yamane, Yuichi
no journal, ,
In the condition such as erroneous transport of nuclear fuel solution in fuel reprocessing plant, criticality approach in reactor and critical assembly, the retrieval work of fuel debris in FUKUSHIMA DAI-ICHI, and so on, in which an amount of reactivity is inserted into nuclear fuel in a subcritical state, an equation is derived which relates the total reactivity to the asymptotic behavior of the power based on one-point kinetics equation. Based on the new equation, a reactivity measurement method has been developed. The method was applied to an experimental data to find that the difference between the experimental and estimated reactivities was 4%.
