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Journal Articles

Perturbation-theory-based sensitivity analysis of prompt neutron decay constant for water-only system

Endo, Tomohiro*; Noguchi, Akihiro*; Yamamoto, Akio*; Tada, Kenichi

Transactions of the American Nuclear Society, 124(1), p.184 - 187, 2021/06

This study confirmed that the sensitivity analysis of the alpha-eigenvalue can be carried even for non-neutron multiplication systems such as water-only systems. The preliminary results of nuclear data-induced uncertainties of alpha-eigenvalue were smaller than the differences between numerical and experimental results of alpha-eigenvalue. For further investigation, it is necessary to reconsider the experimental bias and the nuclear data-induced uncertainty in alpha-eigenvalue due to the thermal scattering law data of water.

Journal Articles

Bayesian uncertainty evaluation of Charpy ductile-to-brittle transition temperature for reactor pressure vessel steels

Takamizawa, Hisashi; Nishiyama, Yutaka; Hirano, Takashi*

Proceedings of ASME 2020 Pressure Vessels and Piping Conference (PVP 2020) (Internet), 7 Pages, 2020/08

https://doi.org/10.1115/PVP2020-21698

no abstracts in English

Journal Articles

Monte Carlo uncertainty quantification of the effective delayed neutron fraction

Iwamoto, Hiroki; Stankovskiy, A.*; Fiorito, L.*; Van den Eynde, G.*

Journal of Nuclear Science and Technology, 55(5), p.539 - 547, 2018/05

https://doi.org/10.1080/00223131.2017.1416691

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 $beta_{rm eff}$ 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 $beta_{rm eff}$ uncertainty. For validation of the calculated $beta_{rm eff}$ , 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 $beta_{rm eff}$ 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 $beta_{rm eff}$ . Finally, total $beta_{rm eff}$ 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 $^{235}$ U.