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A platform for research: civil engineering, architecture and urbanism
Safety Analysis of the US Dual Coolant Liquid Lead-Lithium ITER Test Blanket Module
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.
Safety Analysis of the US Dual Coolant Liquid Lead-Lithium ITER Test Blanket Module
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.
Safety Analysis of the US Dual Coolant Liquid Lead-Lithium ITER Test Blanket Module
B. Merrill (author) / S. Reyes (author) / M. Sawan (author) / C. Wong (author)
2006
7 pages
Report
No indication
English
Thermonuclear Fusion Devices , Reactor Engineering & Nuclear Power Plants , Computers, Control & Information Theory , Physics , Physical & Theoretical Chemistry , ITER reactor , Test blanket module , DEMO blanket concept , Safety analysis , MELCOR computer code , Dual coolant liquid lead-lithium (DCLL) DEMO blanket concept , International Thermonuclear Experimental Reactor (ITER) , Test Blanket Module (TBM)
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