Development of safety analysis code for SCWR and its LOCA analysis of CSR1000

Author:

Jiang ChaofeiORCID,Yu Guojun,Tian Wenxi,Qiu Suizheng,Su G.H.

Funder

Natural Science Foundation of China

Fok Ying Tung Education Foundation

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference41 articles.

1. Antoni, O., Dumaz, P., 2003. Preliminary calculations of a supercritical light water reactor concept using the CATHARE code. In: Proceedings of the 2003 International Congress on Advances in Nuclear Power Plants, Córdoba, Spain, May 4-7.

2. Correlation for boiling heat transfer to saturated fluids in convective flow;Chen;Ind. Eng. Chem. Process Des. Dev.,1966

3. Chen, Y.Z., Yang, C.S., Zhao, M.F., Du, K.W., Zhang, S.M., 2010. Experimental studies on critical flow and heat transfer of water for near-critical and supercritical pressures. In: Proceedings of the IAEA Technical Meeting on Heat Transfer, Thermal-Hydraulics and System Design for Supercritical Pressure Water Cooled Reactors, Pisa, Italy, July 5–8.

4. A mixed core for supercritical water-cooled reactors;Cheng;Nucl. Eng. Technol.,2008

5. Numerical research on the neutronic/thermal[HYPHEN]hydraulic/mechanical coupling characteristics of the optimized helium cooled solid breeder blanket for CFETR;Cui;Fusion Eng. Des.,2017

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