Analysis of Sensitivity and Uncertainty of Calculated <i>k</i><sub>eff</sub> to Nuclear Data on China Experimental Fast Reactor

Yang Jun; Yu Hong; Xu Li; Hu Yun

doi:10.13832/j.jnpe.2014.S2.0071

Volume 35 Issue S2

Feb. 2025

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Yang Jun, Yu Hong, Xu Li, Hu Yun. Analysis of Sensitivity and Uncertainty of Calculated keff to Nuclear Data on China Experimental Fast Reactor[J]. Nuclear Power Engineering, 2014, 35(S2): 71-75. doi: 10.13832/j.jnpe.2014.S2.0071

Citation:

Yang Jun, Yu Hong, Xu Li, Hu Yun. Analysis of Sensitivity and Uncertainty of Calculated k_eff to Nuclear Data on China Experimental Fast Reactor[J]. Nuclear Power Engineering, 2014, 35(S2): 71-75. doi: 10.13832/j.jnpe.2014.S2.0071

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Analysis of Sensitivity and Uncertainty of Calculated k_eff to Nuclear Data on China Experimental Fast Reactor

doi: 10.13832/j.jnpe.2014.S2.0071

Department of Fast Reactor Research and Design, China Institute of Atomic Energy, Beijing, China

Received Date: 2014-11-06
Rev Recd Date: 2014-12-17

Available Online: 2025-02-15

Abstract

Abstract

In order to analyze the nuclear data uncertainty of k_eff for CEFR, the formula of sensitivity to k_eff was derived based on the first order perturbation theory, and the multi-group diffusion nodal method was selected to solve the formula. A sensitivity and uncertainty analysis code named SUAPH was developed, based on Neutronics Analysis System for Fast Reactor（NAS）, and verified. Based on the available covariance matrixes, the sensitivity and uncertainty analysis of k_eff of the first loading on CEFR was done, and the uncertainty value of calculated k_eff due to nuclear data was about 2.02%.
- Nuclear data,
- Sensitivity,
- k_eff calculation uncertainty,
- First order perturbation,
- Neutronics analysis system of fast reactor system(NAS),
- Direct fitting method