Monte Carlo uncertainty quantification of the effective delayed neutron fraction

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Monte Carlo uncertainty quantification of the effective delayed neutron fraction. / Iwamoto, Hiroki; Stankovskiy, Alexey; Fiorito, Luca; Van den Eynde, Gert.

In: Journal of Nuclear Science and Technology, Vol. 55, No. 5, 04.04.2018, p. 539-547.

Research output: Contribution to journalArticlepeer-review

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@article{105559385a854e7992a94d028347d11a,
title = "Monte Carlo uncertainty quantification of the effective delayed neutron fraction",
abstract = "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 βeff 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 βeff uncertainty. For validation of the calculated βeff, a critical configuration of the VENUS-F zero-power reactor was used. It is demonstrated that Chiba{\textquoteright}s modified k-ratio method is superior to Bretscher{\textquoteright}s prompt k-ratio method in terms of reducing the statistical uncertainty in calculating not only βeff 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{\textquoteright}s modified k-ratio method is the most practical for uncertainty quantification of βeff. Finally, total βeff 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-235.",
keywords = "Effective delayed neutron fraction, uncertainty quantification, sensitivity, bretscher's prompt k-ratio method, Chiba's modified k-ratio method, random-sampling method, MCNP, VENUS-F",
author = "Hiroki Iwamoto and Alexey Stankovskiy and Luca Fiorito and {Van den Eynde}, Gert",
note = "Score=10",
year = "2018",
month = apr,
day = "4",
doi = "10.1080/00223131.2017.1416691",
language = "English",
volume = "55",
pages = "539--547",
journal = "Journal of Nuclear Science and Technology",
issn = "1881-1248",
publisher = "Nihon Genshiryoku Gakkai",
number = "5",

}

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TY - JOUR

T1 - Monte Carlo uncertainty quantification of the effective delayed neutron fraction

AU - Iwamoto, Hiroki

AU - Stankovskiy, Alexey

AU - Fiorito, Luca

AU - Van den Eynde, Gert

N1 - Score=10

PY - 2018/4/4

Y1 - 2018/4/4

N2 - 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 βeff 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 βeff uncertainty. For validation of the calculated βeff, a critical configuration of the VENUS-F zero-power reactor was used. It is demonstrated that Chiba’s modified k-ratio method is superior to Bretscher’s prompt k-ratio method in terms of reducing the statistical uncertainty in calculating not only βeff 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 k-ratio method is the most practical for uncertainty quantification of βeff. Finally, total βeff 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-235.

AB - 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 βeff 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 βeff uncertainty. For validation of the calculated βeff, a critical configuration of the VENUS-F zero-power reactor was used. It is demonstrated that Chiba’s modified k-ratio method is superior to Bretscher’s prompt k-ratio method in terms of reducing the statistical uncertainty in calculating not only βeff 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 k-ratio method is the most practical for uncertainty quantification of βeff. Finally, total βeff 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-235.

KW - Effective delayed neutron fraction

KW - uncertainty quantification

KW - sensitivity

KW - bretscher's prompt k-ratio method

KW - Chiba's modified k-ratio method

KW - random-sampling method

KW - MCNP

KW - VENUS-F

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/28873098

U2 - 10.1080/00223131.2017.1416691

DO - 10.1080/00223131.2017.1416691

M3 - Article

VL - 55

SP - 539

EP - 547

JO - Journal of Nuclear Science and Technology

JF - Journal of Nuclear Science and Technology

SN - 1881-1248

IS - 5

ER -

ID: 4065255