Effect of cross section uncertainties on criticality benchmark problem analysis by McCARD

H. J. Park; H. G. Joo; H. J. Shim; C. H. Kim; C. S. Gil

doi:10.3938/jkps.59.1252

Effect of cross section uncertainties on criticality benchmark problem analysis by McCARD

H. J. Park
, H. G. Joo
, H. J. Shim
, C. H. Kim
, C. S. Gil

Research output: Contribution to journal › Article › peer-review

11 Citations (Scopus)

Abstract

A new Monte Carlo (MC) formulation aimed at quantifying effects of both statistical and nuclear cross section uncertainties on neutronics design parameters on nuclear systems is presented. The effectiveness of the formulation is examined through computing the contribution of the cross section uncertainties to the variance of the MC estimate on k_eff of two fast spectrum criticality benchmark problems; GODIVA and JEZEBEL using McCARD as a MC neutronics code and JENDL 3.3 for needed cross section and covariance data. It is shown that the MC formulation is capable of identifying the nuclide and the type of the cross sections that contribute significantly to, and to elicit the necessary improvement in the existing covariance data to reduce, the uncertainties of the criticality calculations.

Original language	English
Pages (from-to)	1252-1255
Number of pages	4
Journal	Journal of the Korean Physical Society
Volume	59
Issue number	23
DOIs	https://doi.org/10.3938/jkps.59.1252
Publication status	Published - Aug 2011

Keywords

Covariance data
Cross section uncertainties
Monte carlo uncertainty analysis formulation
Sensitivity and uncertainty(S/U) analysis

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10.3938/jkps.59.1252

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abstract = "A new Monte Carlo (MC) formulation aimed at quantifying effects of both statistical and nuclear cross section uncertainties on neutronics design parameters on nuclear systems is presented. The effectiveness of the formulation is examined through computing the contribution of the cross section uncertainties to the variance of the MC estimate on keff of two fast spectrum criticality benchmark problems; GODIVA and JEZEBEL using McCARD as a MC neutronics code and JENDL 3.3 for needed cross section and covariance data. It is shown that the MC formulation is capable of identifying the nuclide and the type of the cross sections that contribute significantly to, and to elicit the necessary improvement in the existing covariance data to reduce, the uncertainties of the criticality calculations.",

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year = "2011",

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AU - Park, H. J.

AU - Joo, H. G.

AU - Shim, H. J.

AU - Kim, C. H.

AU - Gil, C. S.

PY - 2011/8

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AB - A new Monte Carlo (MC) formulation aimed at quantifying effects of both statistical and nuclear cross section uncertainties on neutronics design parameters on nuclear systems is presented. The effectiveness of the formulation is examined through computing the contribution of the cross section uncertainties to the variance of the MC estimate on keff of two fast spectrum criticality benchmark problems; GODIVA and JEZEBEL using McCARD as a MC neutronics code and JENDL 3.3 for needed cross section and covariance data. It is shown that the MC formulation is capable of identifying the nuclide and the type of the cross sections that contribute significantly to, and to elicit the necessary improvement in the existing covariance data to reduce, the uncertainties of the criticality calculations.

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KW - Cross section uncertainties

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KW - Sensitivity and uncertainty(S/U) analysis

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Effect of cross section uncertainties on criticality benchmark problem analysis by McCARD

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Keywords

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