Numerical solution of heat transfer process in a prismatic VHTR core accompanying bypass and cross flows
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- 作者：Li Wang ; Qiusheng Liu ; qsliu@maritime.kobe-u.ac.jp" class="auth_mail" title="E-mail the corresponding author ; Katsuya Fukuda
- 关键词：K. Thermal Hydraulics
- 刊名：Nuclear Engineering and Design
- 出版年：2016
- 出版时间：October 2016
- 年：2016
- 卷：307
- 期：Complete
- 页码：275-283
- 全文大小：2829 K
文摘
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Three-dimensional CFD analysis is conducted for the thermal analysis in the reactor core.
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Hot spot temperature, coolant channel outlet temperature distribution are affected by bypass flow.
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Bypass gap size has significant influence on temperature and flow distribution in the core.
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Cross flow has some effect on the temperature distribution of the coolant in the core due to flow mixing in the cross gaps.