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Tuya, D.; Nagaya, Yasunobu
Nuclear Science and Engineering, 15 Pages, 2023/00
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)In Monte Carlo neutron transport calculations for local response or deep penetration problems, some estimation of an importance function is generally required in order to improve their efficiency. In this work, a new recursive Monte Carlo (RMC) method, which is partly based on the original RMC method, for estimating an importance function for local variance reduction (i.e., source-detector type) problems has been developed. The new RMC method has been applied to two sample problems of varying degrees of neutron penetrations, namely a one-dimensional iron slab problem and a three-dimensional concrete-air problem. The biased Monte Carlo calculations with variance reduction parameters based on the obtained importance functions by the new RMC method have been performed to estimate detector responses in these problems. The obtained results are in agreement with those by the reference unbiased Monte Carlo calculations. Furthermore, the biased calculations offered an increase in efficiency on the order of 1 to 10
in terms of the figure of merit (FOM). The results also indicated that the efficiency increased as the neutron penetration became deeper.
Uchiyama, Tomoaki; Oikawa, Tetsukuni; Kondo, Masaaki; Watanabe, Yuichi*; Tamura, Kazuo*
JAERI-Data/Code 2002-011, 205 Pages, 2002/03
JAERI-Data-Code-2002-011.pdf:8.52MB
This report is a user's manual of seismic system reliability analysis code SECOM2 developed at the JAERI for system reliability analysis, which is one of the tasks of seismic probabilistic safety assessment (PSA) of nuclear power plants (NPPs). The SECOM2 code has many functions such as calculation of component and system failure probabilities for given seismic motion levels at the site of an NPP based on the response factor method, calculation of accident sequence frequencies and the core damage frequency (CDF), importance analysis using various indicators, uncertainty analysis, and calculation of the CDF taking into account the effect of the correlations of responses and capacities of components. These analyses require the fault tree (FT) representing the occurrence condition of the system failures and core damage, information about responses and capacities of the components which compose the FT, and seismic hazard curve for the NPP site as input. This report presents calculation method used in the SECOM2 code and how to use those functions in the SECOM2 code.
Homma, Toshimitsu; A.Saltelli*
Reliab. Eng. Syst. Saf., 52, p.1 - 17, 1996/00
Times Cited Count：1310 Percentile：100(Engineering, Industrial)no abstracts in English
Homma, Toshimitsu; A.Saltelli*
Journal of Nuclear Science and Technology, 32(11), p.1164 - 1173, 1995/11
Times Cited Count：28 Percentile：91.05(Nuclear Science & Technology)no abstracts in English
Murata, Isao; Shindo, Ryuichi; Shiozawa, Shusaku
Journal of Nuclear Science and Technology, 32(10), p.971 - 980, 1995/10
Times Cited Count：2 Percentile：28.04(Nuclear Science & Technology)no abstracts in English
Homma, Toshimitsu; A.Saltelli*
EUR-16052, 0, 39 Pages, 1994/00
no abstracts in English
A.Saltelli*; Homma, Toshimitsu; T.Andres*
PC 94: Proc. of 6th Joint EPS-APS Int. Conf. on Physics Computing, 0, p.511 - 514, 1994/00
no abstracts in English
Murata, Isao; Shindo, Ryuichi; Shiozawa, Shusaku
Proc. of the 8th Int. Conf. on Radiation Shielding, p.365 - 370, 1994/00
no abstracts in English
Ishigami, Tsutomu; Homma, Toshimitsu
Proc. of lst Int. Symp. on Uncertainty Modeling and Analysis, p.398 - 403, 1990/12
no abstracts in English
Ishigami, Tsutomu
JAERI-M 89-190, 66 Pages, 1989/11
no abstracts in English
Muramatsu, Ken; Kubo, Kotaro; Takada, Tsuyoshi
no journal, ,
no abstracts in English
