Preliminary study on physical characteristics of single‐pass super‐critical water‐cooled reactor core-Reference-Cited by-同舟云学术

Preliminary study on physical characteristics of single‐pass super‐critical water‐cooled reactor core

Published:2020-08-19 Issue:8 Volume:45 Page:11807-11821
ISSN:0363-907X
Container-title:International Journal of Energy Research
language:en
Short-container-title:Int J Energy Res

Author:

Wang Mingyue¹,Huang Liping¹,Zhang Qian¹,Seidl Marcus²,Liu Zijing³,Wang Xiang¹^ORCID

Affiliation:

1. College of Nuclear Science and Technology Harbin Engineering University Harbin China

2. Department of Nuclear Engineering Technical University of Munich Garching Germany

3. Department of Nuclear Science and Technology University of South China Hengyang China

Funder

Natural Science Foundation of Heilongjiang Province

Publisher

Wiley

Subject

Energy Engineering and Power Technology,Fuel Technology,Nuclear Energy and Engineering,Renewable Energy, Sustainability and the Environment

Link

https://onlinelibrary.wiley.com/doi/pdf/10.1002/er.5764

Reference21 articles.

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2. A MIXED CORE FOR SUPERCRITICAL WATER-COOLED REACTORS

3. Nuclear-based hydrogen production with a thermochemical copper-chlorine cycle and supercritical water reactor: equipment scale-up and process simulation

4. Preliminary safety analysis for the SCWR‐FQT facility;Liu X;International Journal of Energy Research,2019

5. X. M. C. T. MCNP Mcnp—a general purpose monte carlo n‐particle transport code version 5 LA‐UR‐03 1987. The MCNP5 code can be obtained from the Radiation Safety Information Computational Center (RSICC) PO Box 2008. Oak Ridge TN 37831‐6362 5.

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