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Journal Articles

Quasi-Monte Carlo sampling method for simulation-based dynamic probabilistic risk assessment of nuclear power plants

Kubo, Kotaro; Jang, S.*; Takata, Takashi*; Yamaguchi, Akira*

Journal of Nuclear Science and Technology, 59(3), p.357 - 367, 2022/03

 Times Cited Count:0

Dynamic 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.

Journal Articles

Calculation of prompt neutron decay constant with Monte Carlo differential operator sampling

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 ($$alpha$$) with the Monte Carlo method is proposed. It is based on the conventional $$alpha$$-$$k$$ search algorithm but no iteration is required for the $$alpha$$ value search. The $$k$$ eigenvalue is expressed in the truncated Taylor series with regard to $$alpha$$; 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 $$alpha$$ value. The results with the proposed method show good agreement with the reference PNS simulation.

Journal Articles

Impact of perturbed fission source on the effective multiplication factor in Monte Carlo perturbation calculations

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.

Journal Articles

Improvements to a probabilistic fracture mechanics code for evaluating the integrity of a RPV under transient loading

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

Journal Articles

Evaluation of perturbation effect due to fission-source change in eigenvalue problems by Monte Carlo methods

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

JAEA Reports

Current status of uncertainty analysis methods for computer models

Ishigami, Tsutomu

JAERI-M 89-190, 66 Pages, 1989/11

JAERI-M-89-190.pdf:1.5MB

no abstracts in English

JAEA Reports

An importance quantification technique in uncertainty analysis for computer models

Ishigami, Tsutomu; Homma, Toshimitsu

JAERI-M 89-111, 27 Pages, 1989/09

JAERI-M-89-111.pdf:0.68MB

no abstracts in English

JAEA Reports

A Computer Programme for Reactivity Colculation by Cornelatel Sampling Monte Carlo Method

Nakagawa, Masayuki;

JAERI-M 8556, 40 Pages, 1979/11

JAERI-M-8556.pdf:0.96MB

no abstracts in English

Journal Articles

Improvement of correlated sampling Monte Carlo methods for reactivity calculations

Nakagawa, Masayuki;

Journal of Nuclear Science and Technology, 15(6), p.400 - 410, 1978/06

 Times Cited Count:16

no abstracts in English

Oral presentation

Monte Carlo perturbation methods

Nagaya, Yasunobu

no journal, , 

no abstracts in English

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