Numerical scaling assessment on natural circulation in Core Makeup Tank

Author:

Li Xiangbin,Li Haoyong,Liu Yusheng,Wu Qiao,Zhan Benteng

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference20 articles.

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2. Auria F.D., Fruttuoso G., Oriolo F., Bella L., Cavicchia V., SPES-2. AP600 integral test facility results. Confirmatory plant behavior and RELAP5/MOD2. 5 code assessment. ICONE-3: In Proceedings of the 3rd JSME/ASME joint international conference on nuclear engineering. At Kyoto (Japan); 23-27 April 1995, Volume 2.

3. Summary of ROSA-IV LSTF first-phase test program – Integral simulation of PWR small-break LOCAs and transients;Kukita;Nucl. Eng. Des.,1991

4. Integral effect test and code analysis on the cooling performance of the PAFS (passive auxiliary feedwater system) during an FLB (feedwater line break) accident;Bae;Nucl. Eng. Des.,2014

5. Analyses of ACME integral test results on CAP1400 small-break loss-of-coolant-accident transient;Li;Prog. Nucl. Energy,2016

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