Recent progress in safety assessments of Japanese water-cooled solid breeder test blanket module

Fusion Engineering and Design

Volumn 83, Issue 10-12, 2008, Pages 1747-1752

  Tsuru, Daigo ^a   Enoeda, Mikio ^a   Akiba, Masato ^a  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

Author keywords

ACP; FMEA; ITER; Nuclear analysis; ORE; PIE; Test blanket module; Waste; Water cooled solid breeder blanket

Indexed keywords

BREEDING BLANKETS; CLUSTERING ALGORITHMS; COOLING; COOLING SYSTEMS; EARTH BORING MACHINES; EXPERIMENTAL REACTORS; FAILURE ANALYSIS; HEATING; INDUSTRIAL WASTE TREATMENT; LEAKAGE (FLUID); ORE ANALYSIS; ORES; PRESSURIZATION; QUALITY ASSURANCE; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; RADIOACTIVITY; SAFETY FACTOR; TESTING; THERMOELECTRIC EQUIPMENT; TRITIUM; TUNNELING MACHINES; WATER ANALYSIS; WATER COOLED REACTORS; WATER COOLING SYSTEMS;

ACP; FMEA; ITER; NUCLEAR ANALYSIS; PIE; TEST BLANKET MODULE;

BREEDER REACTORS;

EID: 56949104832     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.fusengdes.2008.06.056     Document Type: Article

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