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	1. Cold leg break LOCA Analysis for Canadian-SCWR with passive safety system
	CHAO Fei,YUAN Yuan,WU Pan,SHAN Jianqiang,GOU Junli
	Nuclear Science and Technology 09 May 2016
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	Abstract:Safety analysis is an important issue in SuperCritical Water Reactor concept development. Loss of coolant accident is one of the most important accident which should be treated seriously. The cold leg break LOCA analyses are carried out in this paper to evaluate the feasibility of Canadian SCWR. Passive safety systems, such as automatic depressurization system, accumulator and gravity driven cooling system are applied to mitigate the LOCA consequence. The following conclusions are achieved:1) two cladding temperature peaks will appear in the process of cold leg break LOCA. The discharge flowrate through cold leg break is favourable to decrease the first cladding temperature peak. Automatic depressurization system can decrease the second cladding temperature peak effectively. The first peak cladding temperature in 25% break case is higher than that in 100% break case, while the second peak cladding temperature in 25% break case is lower than that in 100% break case. 2) The peak cladding temperatures of Canadian SCWR with passive safety system under cold leg break LOCA stay below the temperature criterion.
	TO cite this article:CHAO Fei,YUAN Yuan,WU Pan, et al. Cold leg break LOCA Analysis for Canadian-SCWR with passive safety system[OL].[ 9 May 2016] http://en.paper.edu.cn/en_releasepaper/content/4687309


	2. Proposal of a new fuel assembly design for supercritical water cooled reactor
	LIU Xiaojing,CHENG Xu
	Nuclear Science and Technology 05 May 2014
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	Abstract:The supercritical water cooled reactor (SCWR) is a Light Water Reactor (LWR) operating at higher pressure and temperature. Operation above the critical pressure eliminates coolant boiling phenomenon so that the coolant remains single-phase throughout the reactor. Due to its high thermal efficiency and economical competitiveness, SCWR has achieved significant interests of nuclear industries and research institutions. R&D programs have been launched worldwide to study the phenomena involved in SCWR. Design of fuel assemblies of thermal SCWR is one of the main challenging tasks due to: complicated fuel assembly configurations and strong coupling effect of thermal-hydraulics with neutron-kinetics. Although a large number of fuel assembly designs have been proposed, no agreement has been achieved. Further activities are thus needed to develop reliable numerical analysis tools and to propose and assess new fuel assembly designs. In the present paper, new design concepts of SCWR fuel assembly were proposed. The thermal-hydraulic performance and neutron-physical behavior of the new fuel assemblies were investigated using the newly developed coupled code. The results achieved so far indicate the new fuel assembly design has a more uniform distribution of the power density and the coolant temperature compared to the previous ones.
	TO cite this article:LIU Xiaojing,CHENG Xu. Proposal of a new fuel assembly design for supercritical water cooled reactor[OL].[ 5 May 2014] http://en.paper.edu.cn/en_releasepaper/content/4595492

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