Partial flow blockage analysis of the hottest fuel assembly in SNCLFR-100 reactor core

作     者：Kang-Li Shi Shu-Zhou Li Xi-Lin Zhang Peng-Cheng Zhao Hong-Li Chen 

作者机构：School of Nuclear Science and Technology University of Science and Technology of China 

出 版 物：《Nuclear Science and Techniques》 (核技术（英文）)

年 卷 期：2018年第29卷第1期

页      面：110-117页

核心收录：

学科分类：08[工学] 0807[工学-动力工程及工程热物理] 0827[工学-核科学与技术] 0703[理学-化学] 0702[理学-物理学] 0801[工学-力学（可授工学、理学学位）] 

主　　题：Transient analysis Flow blockage LFR Natural circulation RELAP5 code 

摘      要：In this paper, we perform an unprotected partial flow blockage analysis of the hottest fuel assembly in the core of the SNCLFR-100 reactor, a 100 MW_(th) modular natural circulation lead-cooled fast reactor, developed by University of Science and Technology of China. The flow blockage shall cause a degradation of the heat transfer between the fuel assembly and the coolant potentially,which can eventually result in the clad fusion. An analysis of core blockage accidents in a single assembly is of great significance for LFR. Such scenarios are investigated by using the best estimation code RELAP5. Reactivity feedback and axial power profile are considered. The crosssectional fraction of blockage, axial position of blockage,and blockage-developing time are discussed. The cladding material failure shall be the biggest challenge and shall be a considerable threat for integrity of the fuel assembly if the cross-sectional fraction of blockage is over 94%. The blockage-developing time only affects the accident progress. The consequence will be more serious if the axial position of a sudden blockage is closer to the core *** method of analysis procedure can also be applied to analyze similar transient behaviors of other fuel-type reactors.