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Volumn 483, Issue , 2004, Pages 61-68

Validation of stress corrosion cracking model for high level radioactive-waste packages

Author keywords

[No Author keywords available]

Indexed keywords

METALLURGICAL SUSCEPTIBILITY; THRESHOLD STRESS; WASTE PACKAGE; WATER FILM;

EID: 7744230948     PISSN: 0277027X     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1115/PVP2004-2784     Document Type: Conference Paper
Times cited : (1)

References (15)
  • 1
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    • Fracture mechanics data and modeling of environmental cracking of nickel-base alloys in high temperature water
    • Paper No. 44, March 11-15, 1991, NACE
    • Andresen, P.L. 1991, "Fracture Mechanics Data and Modeling of Environmental Cracking of Nickel-Base Alloys in High Temperature Water," Paper No. 44, Corrosion 91, March 11-15, 1991, NACE.
    • (1991) Corrosion 91
    • Andresen, P.L.1
  • 3
    • 0242674808 scopus 로고    scopus 로고
    • Stress corrosion cracking growth rate behavior of alloy 22 (UNS N06022) in concentrated groudwater
    • The annual conference and corrosion show sponsored by NACE International. Paper No. 03683
    • Andresen, P.L., Emigh, P.W., Young, L.M., and Gordon, G.M. 2003, "Stress Corrosion Cracking Growth Rate Behavior of Alloy 22 (UNS N06022) in Concentrated Groudwater," Corrosion 2003. The annual conference and corrosion show sponsored by NACE International. Paper No. 03683.
    • (2003) Corrosion 2003
    • Andresen, P.L.1    Emigh, P.W.2    Young, L.M.3    Gordon, G.M.4
  • 4
    • 0024054216 scopus 로고
    • Life prediction by mechanistic modeling and system monitoring of environmental cracking of iron and nickel alloys in aqueous systems
    • Andresen, P.L. and Ford, F.L. 1988, "Life Prediction by Mechanistic Modeling and System Monitoring of Environmental Cracking of Iron and Nickel Alloys in Aqueous Systems," Materials Science and Engineering, A103, pp. 167-184.
    • (1988) Materials Science and Engineering , vol.A103 , pp. 167-184
    • Andresen, P.L.1    Ford, F.L.2
  • 5
    • 85039430833 scopus 로고    scopus 로고
    • Stress corrosion crack growth rate behavior of Ni alloys 182 and 600 in high temperature water
    • Paper No. 02510, NACE, March 2002
    • Andresen, P.L., Young, L.M., Emigh, P.W., and Horn, R.M. 2002b, "Stress Corrosion Crack Growth Rate Behavior of Ni alloys 182 and 600 in High Temperature Water," Paper No. 02510, Corrosion 2002, NACE, March 2002.
    • (2002) Corrosion 2002
    • Andresen, P.L.1    Young, L.M.2    Emigh, P.W.3    Horn, R.M.4
  • 9
    • 0242674805 scopus 로고    scopus 로고
    • BBA000000-01717-2500-00006 REV 00. Civilian Radioactive Waste Management System (CRWMS) Management and Operation Contractor (M&O), Las Vegas, Nevada
    • CRWMS M&O 1996, Waste Package Closure Weld Development Report. BBA000000-01717-2500-00006 REV 00. Civilian Radioactive Waste Management System (CRWMS) Management and Operation Contractor (M&O), Las Vegas, Nevada.
    • (1996) Waste Package Closure Weld Development Report
  • 10
    • 0003854673 scopus 로고    scopus 로고
    • DOE/RW-0539. Washington, D.C.: U.S. Department of Energy, Office of Civilian Radioactive Waste Management May 2001
    • DOE (U.S. Department of Energy) 2001, Yucca Mountain Science and Engineering Report. DOE/RW-0539. Washington, D.C.: U.S. Department of Energy, Office of Civilian Radioactive Waste Management May 2001.
    • (2001) Yucca Mountain Science and Engineering Report
  • 13
    • 0242694895 scopus 로고    scopus 로고
    • Modeling of stress corrosion cracking for high level radioactive-waste packages
    • PVP. The American Society of Mechanical Engineering. New York, NY
    • Lu, S.C., Gordon, G.M., Andresen, P.L., and Herrera, M.L. 2003, "Modeling of Stress Corrosion Cracking for High Level Radioactive-Waste Packages." Transportation, Storage, and Disposal of Radioactive Materials - 2003. PVP-Vol. 467. The American Society of Mechanical Engineering. New York, NY. pp. 119-127.
    • (2003) Transportation, Storage, and Disposal of Radioactive Materials - 2003 , vol.467 , pp. 119-127
    • Lu, S.C.1    Gordon, G.M.2    Andresen, P.L.3    Herrera, M.L.4
  • 15
    • 14344251002 scopus 로고    scopus 로고
    • Constant load SCC of proposed waste package materials in mixed salt solutions
    • Eleventh International Conference on Environmental Degradation of Materials in Nuclear Power Systems -Water Reactors, August 10-14, 2003, Stevenson, WA
    • Young, L.M., Catlin, G.M., Andresen, P.L., and Gordon, G.M. 2003, "Constant Load SCC of Proposed Waste Package Materials in Mixed Salt Solutions," Eleventh International Conference on Environmental Degradation of Materials in Nuclear Power Systems -Water Reactors, August 10-14, 2003, Stevenson, WA., American Nuclear Society Conference Proceedings, pp. 267-279.
    • (2003) American Nuclear Society Conference Proceedings , pp. 267-279
    • Young, L.M.1    Catlin, G.M.2    Andresen, P.L.3    Gordon, G.M.4


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.