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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：67.01(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.
Katakura, Junichi*; Minato, Futoshi
JAEA-Data/Code 2015-030, 97 Pages, 2016/03
JAEA-Data-Code-2015-030.pdf:1.01MB
JENDL Decay Data File 2015 (JENDL/DDF-2015) has been produced. The decay data of nuclides with mass numbers from 1 to 260 are included. The nuclides with unknown 
- and/or beta-emission are also included in order to keep decay chains. The data of 1,284 fission product nuclides with mass from 66 to 172 remain unchanged from JENDL/FPD-2011 except several corrections which had been claimed by users, and those of the newly added 1,953 nuclides are taken from ENSDF. Finally, the decay data of 3,237 nuclides including 244 stable nuclides were compiled as JENDL/DDF-2015 file.
; Numata, Kazuyuki*; ; *; Oigawa, Hiroyuki*
JNC TY9400 2000-006, 162 Pages, 2000/04
JNC-TY9400-2000-006.pdf:4.57MB
no abstracts in English
Yokoyama, Kenji*; Numata, Kazuyuki*; Ishikawa, Makoto*; Oigawa, Hiroyuki; Iijima, Susumu
JNC-TY9400 2000-006, 168 Pages, 2000/04
no abstracts in English
Katakura, Junichi
JAERI-Conf 99-007, 133 Pages, 1999/07
no abstracts in English
Parish, T. A.*; Charlton, W. S.*; Shinohara, Nobuo; Ando, Masaki; Brady, M. C.*; Raman, S.*
Nuclear Science and Engineering, 131(2), p.208 - 221, 1999/02
Times Cited Count：8 Percentile：53.55(Nuclear Science & Technology)no abstracts in English
Shinohara, Nobuo; Hatsukawa, Yuichi; ; Kono, Nobuaki; Ando, Masaki; H.H.Saleh*; W.S.Charlton*; Parish, T. A.*; S.Raman*
Journal of Radioanalytical and Nuclear Chemistry, 239(3), p.631 - 638, 1999/00
Times Cited Count：3 Percentile：28.64(Chemistry, Analytical)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
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
*
PNC TN9410 92-278, 347 Pages, 1992/09
A series of critical experiments for conventional two-zone homogeneous cores of 6 to 8 MWe-class LMFBR, JUPITER phase-I, were analyzed and evaluated using the latest analytical method, which had been established from the preceding numerous studies on fast reactor physics. The present work is a part of efforts to develop a standard data base for LMFBR core nuclear design at PNC. The analytical method and results are summarized as follows: (1)Analytical method (a)Nuclear data : 70-group fast reactor constant set JFS-3-J2(1989 edition) based on the Japanese Evaluated Nudear Data Library, version 2 (JENDL-2). (b)Cell calculation : plate stretch model, cell heterogeneity treatment by Tone's method and transport cross-sections weighted with neutron current. (c)Base core calculation : 18-group, three-dimensiona1 XYZ diffusion theory and Benoist's anisotropic diffusion coefficients. (d)Correction calculation : three-dimensional transport effect, mesh size effect, cell asymmetric effect and all master model effect etc. (2)Analytical results (a)The C.E (calculation/experiment) values of criticality agree quite well among seven cores (ZPPR-9
10D/2) and do not depend on the core volume or the number of control rod positions (CRP). (b)The C/E values of control rod worths increase gradually from the core center to the core edge positions in each core (511%). Those of reaction rate distributions also indicate similar spatial variations (25%), which is considered to be consistent with the C/E tendency of control rod worths. (c)The reaction rate ratios of C28/F49 and F25/49 give quite stable C/E values of 1.06 and 1.03, respectively. (d)The C/E values of sodium void reactivities are overestimated by +25% at core center region. The C/E dependence on void region size, which was pointed out in the past analyses, is found in the ZPPR-9 core, but not in the ZPPR-10 series. (e)The C/E dependence of 4% on the radial positions were found in sample ...
; *; *; ;
JAERI-M 84-118, 61 Pages, 1984/07
no abstracts in English
JAERI-M 9999, 358 Pages, 1982/03
no abstracts in English
-loaded sodium in-pile loop; *; *; ; ; ;
IEEE Transactions on Nuclear Science, 25(1), p.266 - 277, 1978/01
Times Cited Count：1no abstracts in English
; ; *
JAERI-M 6993, 51 Pages, 1977/02
no abstracts in English
; ;
IEEE Transactions on Nuclear Science, 23(1), p.363 - 374, 1976/01
Times Cited Count：1no 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
