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

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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 ... continued below

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Merrill, Brad; Reyes, Susana; Sawan, Mohamed & Wong, Clement July 1, 2006.

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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.

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  • IAEA 8th Technical Meeting on Fusion Reactor Safety,Vienna, Austria,07/10/2006,07/14/2006

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  • Report No.: INL/CON-06-11506
  • Grant Number: DE-AC07-99ID-13727
  • Office of Scientific & Technical Information Report Number: 912890
  • Archival Resource Key: ark:/67531/metadc883909

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • July 1, 2006

Added to The UNT Digital Library

  • Sept. 22, 2016, 2:13 a.m.

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  • Dec. 12, 2016, 7:56 p.m.

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Merrill, Brad; Reyes, Susana; Sawan, Mohamed & Wong, Clement. Safety Analysis of the US Dual Coolant Liquid Lead-Lithium ITER Test Blanket Module, article, July 1, 2006; [Idaho Falls, Idaho]. (digital.library.unt.edu/ark:/67531/metadc883909/: accessed December 17, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.