메뉴 건너뛰기




Volumn 40, Issue 1, 2003, Pages 39-43

Influence of Dissolved Hydrogen on Oxide Film and PWSCC of Alloy 600 in PWR Primary Water

Author keywords

Alloy 600; Corrosion behavior; Dissolved hydrogen; Oxide film; Primary water stress corrosion cracking; PWR type reactors

Indexed keywords

COMPOSITION EFFECTS; CURRENT DENSITY; ELECTROCHEMISTRY; FILMS; HYDROGEN; MATERIALS TESTING; NICKEL ALLOYS; POLARIZATION; STRESS CORROSION CRACKING; THERMAL EFFECTS;

EID: 0037221248     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.2003.9715330     Document Type: Article
Times cited : (43)

References (15)
  • 4
    • 0012351758 scopus 로고
    • U-bend tube cracking in steam generators
    • G. J. Theus, “U-bend tube cracking in steam generators,” Proc. EPRI Workshop, p. 153 (1981).
    • (1981) Proc. EPRI Workshop , pp. 153
    • Theus, G.J.1
  • 5
    • 0012250092 scopus 로고
    • Environmental degradation of materials in nuclear power systems—water reactors
    • G. P. Airey, “Environmental degradation of materials in nuclear power systems—water reactors,” Proc. Int. Symp., p. 462 (1983).
    • (1983) Proc. Int. Symp. , pp. 462
    • Airey, G.P.1
  • 6
    • 0012250512 scopus 로고
    • [in Japanese]
    • K. Nakayama, Zairyou, 46[455], 967 (1991), [in Japanese].
    • (1991) Zairyou , vol.46 , Issue.455 , pp. 967
    • Nakayama, K.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.