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Volumn , Issue , 1999, Pages 1079-1087

Microstructural, microchemical and hardening evolution in LWR-irradiated austenitic stainless steel

Author keywords

[No Author keywords available]

Indexed keywords

CORROSION RESISTANCE; GRAIN BOUNDARIES; HARDNESS; IRRADIATION; LIGHT WATER REACTORS; MASS SPECTROMETRY; METALLOGRAPHIC MICROSTRUCTURE; RADIATION EFFECTS; STRESS CORROSION CRACKING; TRANSMISSION ELECTRON MICROSCOPY;

EID: 0033489304     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1002/9781118787618.ch113     Document Type: Conference Paper
Times cited : (7)

References (12)
  • 1
    • 0028483357 scopus 로고
    • A review of irradiation assisted stress corrosion cracking
    • P. Scott, "A Review of Irradiation Assisted Stress Corrosion Cracking," J. Nucl. Mat., 211 (1994) 101.
    • (1994) J. Nucl. Mat. , vol.211 , pp. 101
    • Scott, P.1
  • 6
    • 0013011669 scopus 로고    scopus 로고
    • Relationship of radiation-induced segregation phenomena to IASCC
    • Final Report, X103-20, EPRI, August
    • S. M. Bruemmer, L. E. Thomas, L. A. Charlot and B. W. Arey, "Relationship of Radiation-Induced Segregation Phenomena to IASCC", Final Report, X103-20, EPRI, August 1998.
    • (1998)
    • Bruemmer, S.M.1    Thomas, L.E.2    Charlot, L.A.3    Arey, B.W.4
  • 9
    • 0012957899 scopus 로고
    • Deformability of austenitic stainless steels and ni-base alloys in the core of a boiling and a pressurized water reactor
    • ed. G. J. Theus and J. R. Weeks, The Minerals, Metals & Materials Society
    • F. Garzarolli, D. Alter, P. Dewes and J. L. Nelson, "Deformability of Austenitic Stainless Steels and Ni-Base Alloys in the Core of a Boiling and a Pressurized Water Reactor," 3rd Int. Sym. Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, ed. G. J. Theus and J. R. Weeks, The Minerals, Metals & Materials Society, 1988, p. 657.
    • (1988) 3rd Int. Sym. Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors , pp. 657
    • Garzarolli, F.1    Alter, D.2    Dewes, P.3    Nelson, J.L.4
  • 10
    • 0012911059 scopus 로고
    • Deformability of austenitic stainless steels and ni-base alloys in the core of a boiling and a pressurized water reactor
    • ed. J. Roberts and J. R. Weeks, American Nuclear Society
    • F. Garzarolli, D. Alter and P. Dewes, "Deformability of Austenitic Stainless Steels and Ni-Base Alloys in the Core of a Boiling and a Pressurized Water Reactor," 2nd Int. Sym. Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, ed. J. Roberts and J. R. Weeks, American Nuclear Society, 1986, p. 131.
    • (1986) 2nd Int. Sym. Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors , pp. 131
    • Garzarolli, F.1    Alter, D.2    Dewes, P.3


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.