Best estimate plus uncertainty analysis of departure from nucleate boiling limiting case with CASL core simulator VERA-CS in response to PWR main steam line break event
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- 作者：C.S. Brown<sup>asup><sup> ; sup><sup>csbrown3@ncsu.edu" class="auth_mail" title="E-mail the corresponding authorsup> ; H. Zhang<sup>bsup><sup> ; sup><sup>Hongbin.Zhang@inl.gov" class="auth_mail" title="E-mail the corresponding authorsup> ; V. Kucukboyaci<sup>csup><sup> ; sup><sup>kucukbvn@westinghouse.com" class="auth_mail" title="E-mail the corresponding authorsup> ; Y. Sung<sup>csup><sup> ; sup><sup>sungy@westinghouse.com" class="auth_mail" title="E-mail the corresponding authorsup>
- 关键词：BEPU ; best estimate plus uncertainty ; CASL ; Consortium for Advanced Simulation of Light Water Reactors ; CC ; correlation coefficient ; CFD ; computational fluid dynamics ; CHF ; critical heat flux ; CTF ; COBRA-TF ; DNB ; departure from nucleate boiling ; DNBR ; departure from nucleate boiling ratio ; EOC ; end of cycle ; FOM ; figure of merit ; HF ; high flow ; HFP ; hot full power ; HPC ; high performance computing ; HZP ; hot zero power ; INL ; Idaho National Laboratory ; LF ; low flow ; LOCA ; loss-of-coolant accident
- 刊名：Nuclear Engineering and Design
- 出版年：2016
- 出版时间：1 December 2016
- 年：2016
- 卷：309
- 期：Complete
- 页码：8-22
- 全文大小：2906 K
文摘
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Best estimate plus uncertainty (BEPU) analyses of PWR core responses under main steam line break (MSLB) accident.
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CASL’s coupled neutron transport/subchannel code VERA-CS.
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Wilks’ nonparametric statistical method.
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MDNBR 95/95 tolerance limit.