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原文传递 Safety Analysis of the US Dual Coolant Liquid Lead-Lithium ITER Test Blanket Module

题名：	Safety Analysis of the US Dual Coolant Liquid Lead-Lithium ITER Test Blanket Module
作者：	Wong, Clement;Sawan, Mohamed;Reyes, Susana;Merrill, Brad;
关键词：	safety, ITER, test blanket70 - PLASMA PHYSICS AND FUSION TECHNOLOGY; AFTER-HEAT REMOVAL; CHEMICAL REACTIONS; COMPUTER CODES; CONFINEMENT; COOLANTS; EXPERIMENTAL REACTORS; HEAT PRODUCTION; HYDROGEN; IAEA; PRESSURIZATION; REACTOR SAFETY; SAFETY ANALYSIS; TESTING; THERMONUCLEAR REACTORS; TRITIUM
摘要：	The US is proposing a prototype of a dual coolant liquid lead-lithium (DCLL) DEMO blanket concept for testing in the International Thermonuclear Experimental Reactor (ITER) as an ITER Test Blanket Module (TBM). Because safety considerations are an integral part of the design process to ensure that this TBM does not adversely impact the safety of ITER, a safety assessment has been conducted for this TBM and its ancillary systems as requested by the ITER project. Four events were selected by the ITER International Team (IT) to address specific reactor safety concerns, such as VV pressurization, confinement building pressure build-up, TBM decay heat removal capability, tritium and activation products release from the TBM system, and hydrogen and heat production from chemical reactions. This paper summarizes the results of this safety assessment conducted with the MELCOR computer code.
报告类型：	科技报告