Terminal solid solubility of hydrogen in unalloyed zirconium by differential scanning calorimetry

Journal of Nuclear Science and Technology

Volumn 41, Issue 9, 2004, Pages 949-952

  Une, Katsumi ^a   Ishimoto, Shinji ^a  

^a Global Nuclear Fuel Japan Co Ltd   (Japan)

Author keywords

BWR fuels; BWR type reactors; Cladding; Differential scanning calorimetry; Hydrides; Hydrogen; Terminal solid solubility; Zircaloy 2; Zirconium; Zirconium alloys

Indexed keywords

BOILING WATER REACTOR (BWR) FUELS; PELLET CLAD INTERACTION (PCI); TERMINAL SOLID SOLUBILITY (TSS); ZIRCALOY-2;

BOILING WATER REACTORS; CLADDING (COATING); DIFFERENTIAL SCANNING CALORIMETRY; DISSOLUTION; HYDRIDES; HYDROGEN; NUCLEAR FUELS; SOLUBILITY; STRESS CORROSION CRACKING; ZIRCONIUM ALLOYS;

ZIRCONIUM;

EID: 9144226528     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.2004.9715569     Document Type: Article

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