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Sensitivity Evaluation of AP1000 Nuclear Power Plant Best Estimation Model
Joint Authors
Source
Science and Technology of Nuclear Installations
Issue
Vol. 2017, Issue 2017 (31 Dec. 2017), pp.1-13, 13 p.
Publisher
Hindawi Publishing Corporation
Publication Date
2017-06-28
Country of Publication
Egypt
No. of Pages
13
Abstract EN
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.
American Psychological Association (APA)
Shi, Hao& Cai, Qi& Chen, Yuqing. 2017. Sensitivity Evaluation of AP1000 Nuclear Power Plant Best Estimation Model. Science and Technology of Nuclear Installations،Vol. 2017, no. 2017, pp.1-13.
https://search.emarefa.net/detail/BIM-1203817
Modern Language Association (MLA)
Shi, Hao…[et al.]. Sensitivity Evaluation of AP1000 Nuclear Power Plant Best Estimation Model. Science and Technology of Nuclear Installations No. 2017 (2017), pp.1-13.
https://search.emarefa.net/detail/BIM-1203817
American Medical Association (AMA)
Shi, Hao& Cai, Qi& Chen, Yuqing. Sensitivity Evaluation of AP1000 Nuclear Power Plant Best Estimation Model. Science and Technology of Nuclear Installations. 2017. Vol. 2017, no. 2017, pp.1-13.
https://search.emarefa.net/detail/BIM-1203817
Data Type
Journal Articles
Language
English
Notes
Includes bibliographical references
Record ID
BIM-1203817