Nuclear aspects of molten salt blankets

Fusion Engineering and Design

Volumn 69, Issue 1-4 SPEC, 2003, Pages 205-213

  Cheng, E T ^a   Merril, B J ^b   Sze, Dai Kai ^c  

^a TSI Research Inc   (United States)

^b IDAHO NATIONAL LABORATORY   (United States)

^c UNIVERSITY OF CALIFORNIA   (United States)

Author keywords

Corrosion control; Molten salt; Nuclear transmutation; Site dose; Tritium breeding

Indexed keywords

BERYLLIUM COMPOUNDS; CORROSION; FUSION REACTIONS; LITHIUM COMPOUNDS;

MOLTEN SALT BLANKETS;

POWER PLANTS;

EID: 0041830716     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0920-3796(03)00339-9     Document Type: Article

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