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Program - Brookhaven National Laboratory

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LC 5 5:00 PM<br />

Uncertainty Study of Nuclear Model Parameters for the n+ 56 Fe Reactions in the Fast<br />

Neutron Region Below 20 MeV<br />

Junfeng Duan, Erwin Alhassan, Cecilia Gustavsson, Stephan Pomp, Henrik Sjöstrand, Michael Osterlund<br />

Division of applied nuclear physics, Department of physics and astronomy, Uppsala University, Box 516,<br />

751 20, Uppsala, Sweden<br />

Arjan Koning, Dimitri Rochman<br />

Nuclear Research and consultancy Group(NRG),P.O. Box 25, 3 Westerduinweg, 1755 ZG Petten, The<br />

Netherlands<br />

With the development of Gen-IV reactors, advanced fuel cycles, transmutation and shielding design, the<br />

need of neutron cross section covariance data (uncertainties and correlations) is becoming increasingly<br />

important. In this work, random parameter variation is applied tothe neutron optical model potential<br />

(OMP) of 56 Fe by using the Total Monte Carlo method [1]. The uncertainties of total, elastic, non-elastic<br />

cross section as well as angular distribution and their correlations have been obtained based on the existing<br />

experimental data. Also, by using a parameter rejection method based on experimental data, a correlation<br />

matrix for the OMP parameters is obtained. The impact of these OMP parameter uncertainties on all<br />

partial channels for n+ 56 Fe reaction is investigated with the TALYS nuclear model code[2]. Furthermore,<br />

the impact of other model parameter uncertainties such as level density and gamma width on each partial<br />

channel is investigated. By using random sampling within the appropriate uncertainty ranges, more than<br />

300 random evaluations of 56 Fe are presented. These are provided for reactor simulation codes for nuclear<br />

data error propagation.<br />

[1] Koning, A.J., and Rochman, D., 2008. Towards sustainable nuclear energy: Putting nuclear physics<br />

to work. Annals of Nuclear Energy 35, p. 2024-230. [2] Koning, A.J., Hilaire S., Duijvestijn, M.C., 2007.<br />

TALYS-1.0. In: Bersillon, O., Gunsing, F., Bauge, E., Jacqmin, R., Leray, S. (Eds.), Proceedings of the<br />

International Conference on Nuclear Data for Science and Technology, Nice, France, 22-27 April, EDP<br />

Sciences, p. 211.<br />

LC 6 5:15 PM<br />

Monte Carlo Sensitivity and Uncertainty Analysis with Continuous-Energy Covariance<br />

Data<br />

Ho Jin Park<br />

Korea Atomic Energy Research Institute<br />

Hyung Jin Shim, Chang Hyo Kim<br />

Seoul <strong>National</strong> University<br />

In the Monte Carlo (MC) sensitivity and uncertainty (S/U) analysis [1] with continuous-energy cross section<br />

libraries, the sensitivities of a tallied parameter can be estimated based on the multi-group relative<br />

covariance data. In our previous study [2], it was presented that the k uncertainties estimated by using<br />

different continuous-energy cross section libraries but the same multi-group covariance data may be significantly<br />

different each other because of limitation of the relative covariance approach. In order to overcome<br />

the multi-group approximation of the covariance data, we present a method to directly use the covariance<br />

files in the MC sensitivity calculations. The k uncertainties due to the multi-group and continuous-energy<br />

covariance data are compared for various criticality benchmark problems.<br />

Corresponding author: Hyung Jin Shim<br />

176

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