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Kubo, Kotaro; Jang, S.*; Takata, Takashi*; Yamaguchi, Akira*
Journal of Nuclear Science and Technology, 59(3), p.357 - 367, 2022/03
Times Cited Count：0Dynamic probabilistic risk assessment (PRA), which handles epistemic and aleatory uncertainties by coupling the thermal-hydraulics simulation and probabilistic sampling, enables a more realistic and detailed analysis than conventional PRA. However, enormous calculation costs are incurred by these improvements. One solution is to select an appropriate sampling method. In this paper, we applied the Monte Carlo, Latin hypercube, grid-point, and quasi-Monte Carlo sampling methods to the dynamic PRA of a station blackout sequence in a boiling water reactor and compared each method. The result indicated that quasi-Monte Carlo sampling method handles the uncertainties most effectively in the assumed scenario.
Nagaya, Yasunobu
Proceedings of Joint International Conference on Mathematics and Computation, Supercomputing in Nuclear Applications and the Monte Carlo Method (M&C + SNA + MC 2015) (CD-ROM), 9 Pages, 2015/04
A new method to calculate the prompt neutron decay constant (
) with the Monte Carlo method is proposed. It is based on the conventional -
search algorithm but no iteration is required for the value search. The eigenvalue is expressed in the truncated Taylor series with regard to ; the differential coefficients are calculated with the differential operator sampling, which is one of the Monte Carlo perturbation techniques. In order to examine the applicability of the proposed method, verification has been performed for simple geometries of a bare fast system (Godiva) and an unreflected thermal system (STACY). Comparisons has been done with the pulsed neutron source (PNS) simulation and the direct calculation from the definition of the value. The results with the proposed method show good agreement with the reference PNS simulation.
Nagaya, Yasunobu; Mori, Takamasa
Journal of Nuclear Science and Technology, 42(5), p.428 - 441, 2005/05
Times Cited Count：50 Percentile：95.28(Nuclear Science & Technology)A new method to estimate a change in the effective multiplication factor due to the perturbed fission source distribution has been proposed for Monte Carlo perturbation calculations with the correlated sampling and differential operator sampling techniques. The method has been implemented into the MVP code for verification. Simple benchmark problems have been set up for fast and thermal systems and the applicability of the method has been verified with the problems. In consequence, it has been confirmed that the method is very effective to estimate the change. It has been also shown that there are some cases where the perturbed source effect is significant and the change in reactivity cannot be estimated accurately without taking the effect into account. Even in such cases, the new method can estimate the perturbed source effect and the estimation of the change in reactivity has been remarkably improved.
Li, Y.*; Kato, Daisuke*; Shibata, Katsuyuki; Onizawa, Kunio
International Journal of Pressure Vessels and Piping, 78(4), p.271 - 282, 2001/04
Times Cited Count：5 Percentile：42.81(Engineering, Multidisciplinary)no abstracts in English
Nagaya, Yasunobu; Mori, Takamasa
Proceedings of the ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium (PHYSOR2000) (CD-ROM), p.13 - 0, 2000/00
no abstracts in English
Homma, Toshimitsu; *
JAERI-M 93-207, 36 Pages, 1993/10
no abstracts in English
Ishigami, Tsutomu
JAERI-M 89-190, 66 Pages, 1989/11
no abstracts in English
Ishigami, Tsutomu; Homma, Toshimitsu
JAERI-M 89-111, 27 Pages, 1989/09
no abstracts in English
Nakagawa, Masayuki;
JAERI-M 8556, 40 Pages, 1979/11
no abstracts in English
Nakagawa, Masayuki;
Journal of Nuclear Science and Technology, 15(6), p.400 - 410, 1978/06
Times Cited Count：16no abstracts in English
