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Heat transfer effectiveness for cooling of Canadian SCWR fuel assembly nder the LOCA/LOECC scenario

发布时间:2025-04-30  点击次数:

发布时间:2025-04-30

论文名称:Heat transfer effectiveness for cooling of Canadian SCWR fuel assembly nder the LOCA/LOECC scenario

发表刊物:Annals of Nuclear Energy

摘要:The effectiveness of heat transfer from the fuel rods to the moderator in a Canadian, pressure-tube type, uper-Critical Water-cooled Reactor (SCWR) has been assessed for the postulated loss-of-coolant accident LOCA) coupled with the total loss of emergency core cooling (LOECC) event using the safety analysis ode ‘‘SCTRAN’’. A radiation heat-transfer model, including a two-dimensional heat conduction solution cheme, has been incorporated into the SCTRAN code for this assessment. The assessment result shows hat the combined radiation heat transfer from the fuel rods to the fuel channel and natural convective eat transfer from the fuel rods to the steam are effective in removing decay heat for the LOCA/LOECC cenario. Maximum cladding temperatures of fuel rods in inner and outer rings of the fuel assembly in he highest-power channel are predicted at 1278 C and 1192 C respectively, which are lower than he melting point of the modified stainless-steel cladding. Sensitivity analyses of several analytical arameters on the predicted maximum cladding temperatures have been performed.

合写作者:Pan Wu, Jianqiang Shan, Junli Gou, Laurence K.H. Leung, Bin Zhang , Bo Zhang

卷号:81 (2015)

页面范围:306–319

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发表时间:2016-03-15

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