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Iwamoto, Hiroki; Stankovskiy, A.*; Fiorito, L.*; Van den Eynde, G.*
Journal of Nuclear Science and Technology, 55(5), p.539 - 547, 2018/05
Times Cited Count：9 Percentile：67.52(Nuclear Science & Technology)The applicability of Monte Carlo techniques, namely the Monte Carlo sensitivity method and the random-sampling method, for uncertainty quantification of the effective delayed neutron fraction 
is investigated using the continuous-energy Monte Carlo transport code, MCNP, from the perspective of statistical convergence issues. This study focuses on the nuclear data as one of the major sources of uncertainty. For validation of the calculated , a critical configuration of the VENUS-F zero-power reactor was used. It is demonstrated that Chiba's modified 
-ratio method is superior to Bretscher's prompt -ratio method in terms of reducing the statistical uncertainty in calculating not only but also its sensitivities and the uncertainty due to nuclear data. From this result and a comparison of uncertainties obtained by the Monte Carlo sensitivity method and the random-sampling method, it is shown that the Monte Carlo sensitivity method using Chiba's modified -ratio method is the most practical for uncertainty quantification of . Finally, total uncertainty due to nuclear data for the VENUS-F critical configuration is determined to be approximately 2.7% with JENDL-4.0u, which is dominated by the delayed neutron yield of 
U.
Yokoyama, Kenji*; Numata, Kazuyuki*; Ishikawa, Makoto*; Oigawa, Hiroyuki; Iijima, Susumu
JNC-TY9400 2000-006, 168 Pages, 2000/04
no abstracts in English
for water-moderated U and U-Pu cores by a method using buckling coefficient of reactivitySuzaki, Takenori; Sakurai, Kiyoshi; Nakajima, Ken; Horiki, Oichiro*
Proceedings of 6th International Conference on Nuclear Criticality Safety (ICNC '99), 1, p.386 - 394, 1999/00
no abstracts in English
Sakurai, Kiyoshi; Yamamoto, Toshihiro
Nihon Genshiryoku Gakkai-Shi, 40(4), p.304 - 311, 1998/00
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
in JAERI-FCASakurai, Takeshi; Okajima, Shigeaki; ; Osugi, Toshitaka; M.Martini*; P.Chaussonnet*; H.Philibert*; I.P.Matveenko*; S.P.Belov*; V.A.Doulin*; et al.
Proc. of Int. Conf. on Physics of Nucl. Science and Technol., 1, p.182 - 189, 1998/00
no abstracts in English
)Okajima, Shigeaki; Sakurai, Takeshi; Mukaiyama, Takehiko
JAERI-Conf 97-005, 00(00), p.71 - 76, 1997/00
no abstracts in English
; ; *
JAERI-M 6993, 51 Pages, 1977/02
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%.
