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Volumn , Issue , 2007, Pages 3-24

An overview of materials degradation by stress corrosion in PWRs

Author keywords

[No Author keywords available]

Indexed keywords

CHEMICAL ENGINEERING; CORROSION;

EID: 77955266802     PISSN: None     EISSN: None     Source Type: Book    
DOI: 10.1533/9781845693466.1.3     Document Type: Chapter
Times cited : (28)

References (32)
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    • (1987) Corrosion , vol.13 , pp. 937-945
    • Green, S.J.1
  • 4
    • 0041881532 scopus 로고    scopus 로고
    • Stress corrosion cracking in Pressurized Water Reactors - Interpretation, modeling and remedies
    • Scott P.M. Stress corrosion cracking in Pressurized Water Reactors - Interpretation, modeling and remedies. Corrosion 2000, 56:771-782.
    • (2000) Corrosion , vol.56 , pp. 771-782
    • Scott, P.M.1
  • 12
  • 15
    • 0347904766 scopus 로고    scopus 로고
    • The use of tube examinations and laboratory simulations to improve the knowledge of local environments and surface reactions in TSPs
    • NACE International, R.W. Staehle, J.A. Gorman, A.R. McIlree (Eds.)
    • Sala B., Combrade P., Gelpi A., Dupin M. The use of tube examinations and laboratory simulations to improve the knowledge of local environments and surface reactions in TSPs. Control of Corrosion on the Secondary Side of Steam Generators 1996, 483-497. NACE International. R.W. Staehle, J.A. Gorman, A.R. McIlree (Eds.).
    • (1996) Control of Corrosion on the Secondary Side of Steam Generators , pp. 483-497
    • Sala, B.1    Combrade, P.2    Gelpi, A.3    Dupin, M.4
  • 16
    • 0023862275 scopus 로고
    • Thermal, hydraulic and corrosion aspects of PWR steam generator problems
    • Green S.J. Thermal, hydraulic and corrosion aspects of PWR steam generator problems. Heat Transfer Engineering 1988, 9:19-68.
    • (1988) Heat Transfer Engineering , vol.9 , pp. 19-68
    • Green, S.J.1
  • 18
    • 0347504609 scopus 로고    scopus 로고
    • Quantitative assessment of submodes of stress corrosion cracking on the secondary side of steam generator tubing in Pressurized Water Reactors: Parts 1, 2 and 3
    • 60 (2004) 5-63, and 60 (2004) 115-180
    • Staehle R., Gorman J.A. Quantitative assessment of submodes of stress corrosion cracking on the secondary side of steam generator tubing in Pressurized Water Reactors: Parts 1, 2 and 3. Corrosion 2003, 59:931-994. 60 (2004) 5-63, and 60 (2004) 115-180.
    • (2003) Corrosion , vol.59 , pp. 931-994
    • Staehle, R.1    Gorman, J.A.2
  • 20
    • 0000801486 scopus 로고    scopus 로고
    • Experience and assessment of stress corrosion cracking in L-grade stainless steel in BWR internals
    • Horn R.M., Gordon G.M., Ford F.P., Cowan R.L. Experience and assessment of stress corrosion cracking in L-grade stainless steel in BWR internals. Nuclear Engineering and Design 1997, 174:313-325.
    • (1997) Nuclear Engineering and Design , vol.174 , pp. 313-325
    • Horn, R.M.1    Gordon, G.M.2    Ford, F.P.3    Cowan, R.L.4
  • 22
    • 0033338807 scopus 로고    scopus 로고
    • Radiation-induced material changes and susceptibility to Intergranular failure of light-water-reactor core internals
    • Bruemmer S.M., Simonen E.P., Scott P.M., Andresen P.L., Was G.S., Nelson J.L. Radiation-induced material changes and susceptibility to Intergranular failure of light-water-reactor core internals. Journal of Nuclear Materials 1999, 274:299-314.
    • (1999) Journal of Nuclear Materials , vol.274 , pp. 299-314
    • Bruemmer, S.M.1    Simonen, E.P.2    Scott, P.M.3    Andresen, P.L.4    Was, G.S.5    Nelson, J.L.6
  • 25
    • 84867251714 scopus 로고
    • US NRC Information Notice
    • US NRC Information Notice Valve stem corrosion failures 1985, 59-85.
    • (1985) Valve stem corrosion failures , pp. 59-85
  • 26
    • 0027541525 scopus 로고
    • Aging between 300 and 450°C of wrought martensitic 13-17wt% Cr stainless steels
    • Yrieix B., Guttmann M. Aging between 300 and 450°C of wrought martensitic 13-17wt% Cr stainless steels. Materials Science and Technology 1993, 9:113-125.
    • (1993) Materials Science and Technology , vol.9 , pp. 113-125
    • Yrieix, B.1    Guttmann, M.2
  • 29
    • 0022661569 scopus 로고
    • Strain-induced corrosion cracking of low-alloy steels in LWR systems - Case histories and identification of conditions leading to susceptibility
    • Hickling J., Blind D. Strain-induced corrosion cracking of low-alloy steels in LWR systems - Case histories and identification of conditions leading to susceptibility. Nuclear Engineering and Design 1986, 91:305-330.
    • (1986) Nuclear Engineering and Design , vol.91 , pp. 305-330
    • Hickling, J.1    Blind, D.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.