Study of core flow distribution for small modular natural circulation lead or lead-alloy cooled fast reactors
作者： Zhao Chen , Pengcheng Zhao , Guangming Zhou , Hongli Chen
DOI: 10.1016/J.ANUCENE.2014.04.032
关键词: Flow (psychology) 、 Environmental science 、 Modular design 、 Natural circulation 、 Nuclear reactor 、 Distributor 、 Power (physics) 、 Computational fluid dynamics 、 Nuclear engineering 、 Communication channel
摘要: Abstract Small modular natural circulation lead or lead-alloy cooled fast reactor (LFR) is a potential candidate for LFR development. It has many attractive advantages such as reduced capital costs and inherent safety. The core flow distribution calculation an important issue nuclear design, which will provide input parameters to thermal-hydraulic analysis safety analysis. of different from that forced reactor. In reactor, the can be controlled adjusted by pump power distributor, while in automatically according relationship between local resistance feature. this paper, non-uniform heated parallel channel code was developed comparison study method CFD carried out assess exactness code. optimization design 10MW conducted using A scheme proposed results.
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