Development of the loss coefficient correlation for cross...

Nuclear Engineering and Design 2016 / 10 Vol. 307

Development of the loss coefficient correlation for cross flow between graphite fuel blocks in the core of prismatic very high temperature reactor-PMR200

Lee, Jeong-Hun, Cho, Hyoung-Kyu, Park, Goon-Cherl
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Volume:
307
Language:
english
Journal:
Nuclear Engineering and Design
DOI:
10.1016/j.nucengdes.2016.06.038
Date:
October, 2016
File:
PDF, 4.17 MB
english, 2016
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