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Volumn 347, Issue 1-2, 2005, Pages 12-19

Release of fission tritium through Zircaloy-4 fuel cladding tubes

Author keywords

[No Author keywords available]

Indexed keywords

COOLANTS; NUCLEAR FUEL CLADDING; OXIDATION; REACTION KINETICS; TEMPERATURE DISTRIBUTION; TUBES (COMPONENTS);

EID: 27744527319     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jnucmat.2005.06.008     Document Type: Article
Times cited : (16)

References (35)
  • 24
    • 0004214749 scopus 로고    scopus 로고
    • Waterside corrosion of Zr alloys in nuclear power plants
    • IAEA Vienna
    • Waterside corrosion of Zr alloys in nuclear power plants, IAEA TECDOC 996, IAEA Vienna (1998).
    • (1998) IAEA TECDOC , vol.996
  • 28
    • 0003434380 scopus 로고
    • John Willey New York
    • A. Bejan Heat Transfer 1993 John Willey New York p. 118
    • (1993) Heat Transfer
    • Bejan, A.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.