Development of a Thermal-Hydraulic Analysis Code and...

Journal of Nuclear Engineering and Radiation Science 2015 / 02 Vol. 1; Iss. 1

Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a Fluoride-Salt-Cooled High-Temperature Test Reactor

Xiao, Yao, Hu, Lin-Wen, Qiu, Suizheng, Zhang, Dalin, Guanghui, Su, Tian, Wenxi
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Volume:
1
Language:
english
Journal:
Journal of Nuclear Engineering and Radiation Science
DOI:
10.1115/1.4026394
Date:
February, 2015
File:
PDF, 3.90 MB
english, 2015
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