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Science and Technology of Nuclear Installations - Volume 2017 2017, Article ID 9304520, 13 pages -

Research ArticleDepartment of Nuclear Science and Engineering, Naval University of Engineering, Wuhan 430033, China

Correspondence should be addressed to Qi Cai

Received 18 January 2017; Revised 8 March 2017; Accepted 16 March 2017; Published 28 June 2017

Academic Editor: Arkady Serikov

Copyright © 2017 Hao Shi et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.


The best estimation process of AP1000 Nuclear Power Plant NPP requires proper selections of parameters and models so as to obtain the most accurate results compared with the actual design parameters. Therefore, it is necessary to identify and evaluate the influences of these parameters and modeling approaches quantitatively and qualitatively. Based on the best estimate thermal-hydraulic system code RELAP5-MOD3.2, sensitivity analysis has been performed on core partition methods, parameters, and model selections in AP1000 Nuclear Power Plant, like the core channel number, pressurizer node number, feedwater temperature, and so forth. The results show that core channel number, core channel node number, and the pressurizer node number have apparent influences on the coolant temperature variation and pressure drop through the reactor. The feedwater temperature is a sensitive factor to the Steam Generator SG outlet temperature and the Steam Generator outlet pressure. In addition, the cross-flow model nearly has no effects on the coolant temperature variation and pressure drop in the reactor, in both the steady state and the loss of power transient. Furthermore, some fittest parameters with which the most accurate results could be obtained have been put forward for the nuclear system simulation.

Author: Hao Shi, Qi Cai, and Yuqing Chen



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