TY - GEN
T1 - Nuclear data uncertainty propagation analysis for LWR depletion calculation
AU - Cao, Liangzhi
AU - Yang, Chao
AU - Zu, Tiejun
AU - Wu, Hongchun
PY - 2016
Y1 - 2016
N2 - In order to assess the uncertainties induced by nuclear cross sections in the depletion calculation, a computational code named SUNDEW has been developed based on the home-developed lattice code CACTI. In the SUNDEW, Generalized Perturbation Theory (GPT) is applied to calculate sensitivity coefficient of response functions with respect to the nuclear cross sections. Method of Characteristic (MOC) is employed to solve the transport equation, adjoint and generalized adjoint transport equation. Chebyshev Rational Approximation Method (CRAM) is implemented to solve the depletion equation and adjoint depletion equation. The sensitivity coefficients of Keffand nuclide density with respect to the nuclear cross sections are verified by comparing with the calculation results of direct perturbation calculation (DP). The uncertainties of ATeff and number density are analyzed for the PWR burn-up pin-cell benchmark proposed by the NEA/OECD. The numerical results with ENDF/B-VII.1 covariance data are compared with those from JENDL4.0 covariance data, which reveal that the uncertainties assessment and the source of covariance data have a strong relationship. In addition, to identify the cross section improvement priority for nuclide, reaction and energy range, the dominant contributors of the Keff and number density uncertainties are analyzed in different depletions.
AB - In order to assess the uncertainties induced by nuclear cross sections in the depletion calculation, a computational code named SUNDEW has been developed based on the home-developed lattice code CACTI. In the SUNDEW, Generalized Perturbation Theory (GPT) is applied to calculate sensitivity coefficient of response functions with respect to the nuclear cross sections. Method of Characteristic (MOC) is employed to solve the transport equation, adjoint and generalized adjoint transport equation. Chebyshev Rational Approximation Method (CRAM) is implemented to solve the depletion equation and adjoint depletion equation. The sensitivity coefficients of Keffand nuclide density with respect to the nuclear cross sections are verified by comparing with the calculation results of direct perturbation calculation (DP). The uncertainties of ATeff and number density are analyzed for the PWR burn-up pin-cell benchmark proposed by the NEA/OECD. The numerical results with ENDF/B-VII.1 covariance data are compared with those from JENDL4.0 covariance data, which reveal that the uncertainties assessment and the source of covariance data have a strong relationship. In addition, to identify the cross section improvement priority for nuclide, reaction and energy range, the dominant contributors of the Keff and number density uncertainties are analyzed in different depletions.
KW - Depletion calculation
KW - Nuclear data
KW - Uncertainty propagation
UR - https://www.scopus.com/pages/publications/84992153795
M3 - 会议稿件
AN - SCOPUS:84992153795
T3 - Physics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century
SP - 4217
EP - 4230
BT - Physics of Reactors 2016, PHYSOR 2016
PB - American Nuclear Society
T2 - Physics of Reactors 2016: Unifying Theory and Experiments in the 21st Century, PHYSOR 2016
Y2 - 1 May 2016 through 5 May 2016
ER -