The terminal solid solubility of hydrogen in irradiated Zircaloy-2 and microscopic modeling of hydride behavior

Journal of Nuclear Materials

Volumn 389, Issue 1, 2009, Pages 127-136

  Une, K ^a   Ishimoto, S ^a   Etoh, Y ^a   Ito, K ^b   Ogata, K ^c   Baba, T ^c   Kamimura, K ^c   Kobayashi, Y ^d  

^a NIPPON NUCLEAR FUEL DEVELOPMENT CO LTD   (Japan)

^b Global Nuclear Fuel Japan Co Ltd   (Japan)

^c JAPAN NUCLEAR ENERGY SAFETY ORGANIZATION   (Japan)

^d MOX Corporation   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

CLADDING TUBES; DISSOLVED HYDROGENS; FAST NEUTRON FLUENCE; HABIT PLANES; HEATING STAGES; IRRADIATION DEFECTS; MICROSCOPIC ANALYSIS; MICROSCOPIC MODELING; POST-IRRADIATION ANNEALING; STRESS-INDUCED; TERMINAL SOLID SOLUBILITIES; TEXTURED GRAINS; ZIRCALOY-2;

BOILING WATER REACTORS; DIFFERENTIAL SCANNING CALORIMETRY; DISSOLUTION; HYDRIDES; HYDROGEN; REAL TIME SYSTEMS; SOLUBILITY; TERNARY SYSTEMS; ZIRCONIUM ALLOYS;

NEUTRON IRRADIATION;

EID: 64449084344     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jnucmat.2009.01.017     Document Type: Article

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