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Volumn 1, Issue , 2007, Pages 609-631

An overview of the Cooperative IASCC Research (CIR) Program

Author keywords

[No Author keywords available]

Indexed keywords

AUSTENITIC STAINLESS STEEL; AUSTENITIC STEEL; BOILING WATER REACTORS; CONCENTRATION (PROCESS); CORROSION; CRACKING (CHEMICAL); DEGRADATION; ELECTRIC POWER SYSTEMS; ELECTRIC POWER TRANSMISSION NETWORKS; IRRADIATION; LIGHT WATER REACTORS; NUCLEAR ENERGY; POWER TRANSMISSION; PRESSURIZED WATER REACTORS; RESIDUAL STRESSES; STAINLESS STEEL; STEAM POWER PLANTS; WATER COOLED REACTORS;

EID: 51649089970     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (5)

References (23)
  • 3
    • 51649121576 scopus 로고    scopus 로고
    • Development, Evaluation, and Analysis of the Initial CIR -IASCC Database, EPRI, Palo Alto, CA: 1998. TR-108749
    • Development, Evaluation, and Analysis of the Initial CIR -IASCC Database, EPRI, Palo Alto, CA: 1998. TR-108749
  • 4
    • 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. and Nelson, J. L.,"Radiation-Induced Material Changes and Susceptibility to Intergranular Failure of Light- Water-Reactor Core Internals," J. Nucl. Mater., 274(1999) 299-314.
    • (1999) J. Nucl. Mater , 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
  • 9
    • 51649110259 scopus 로고    scopus 로고
    • Analytical Transmission Electron Microscopy (ATEM) Characterization of Stress-Corrosion Cracks in LWR-Irradiated Austenitic Stainless Steel Core Components: Revision 2, EPRI, Palo Alto, CA: 2006. 1014511.
    • Analytical Transmission Electron Microscopy (ATEM) Characterization of Stress-Corrosion Cracks in LWR-Irradiated Austenitic Stainless Steel Core Components: Revision 2, EPRI, Palo Alto, CA: 2006. 1014511.
  • 11
    • 51649125310 scopus 로고    scopus 로고
    • The Use of Proton Irradiation to Determine IASCC Mechanisms in Light Water Reactors: Solute Addition Alloys, EPRI, Palo Alto, CA: 2003. 1007440.
    • The Use of Proton Irradiation to Determine IASCC Mechanisms in Light Water Reactors: Solute Addition Alloys, EPRI, Palo Alto, CA: 2003. 1007440.
  • 12
    • 0036532066 scopus 로고    scopus 로고
    • Isolation of the Role of RadiationInduced Segregation in Irradiation-Assisted Stress Corrosion Cracking of Proton-Irradiated Austenitic Stainless Steels
    • Busby J.T., Was G.S., and Kenik E.A., "Isolation of the Role of RadiationInduced Segregation in Irradiation-Assisted Stress Corrosion Cracking of Proton-Irradiated Austenitic Stainless Steels," J. Nucl. Mater. 302 (2002) p. 20-40.
    • (2002) J. Nucl. Mater , vol.302 , pp. 20-40
    • Busby, J.T.1    Was, G.S.2    Kenik, E.A.3
  • 17
    • 51649123062 scopus 로고    scopus 로고
    • Stress corrosion crack growth behavior of cold-worked 3 04L and 316L stainless steels. EPRI, Palo Alto, CA: 2002.1007379
    • Stress corrosion crack growth behavior of cold-worked 3 04L and 316L stainless steels. EPRI, Palo Alto, CA: 2002.1007379
  • 18
    • 51649114361 scopus 로고    scopus 로고
    • Quantification of yield strength effects on IGSCC in austenitic stainless steels and its implications to the IASCC, EPRI, Palo Alto, CA: 2002. 1007380
    • Quantification of yield strength effects on IGSCC in austenitic stainless steels and its implications to the IASCC, EPRI, Palo Alto, CA: 2002. 1007380
  • 20
    • 51649103647 scopus 로고    scopus 로고
    • CIR II Program: Crack Growth Testing of Fast Reactor Irradiated Type 304L Stainless Steel in BWR Environments, EPRI, Palo Alto, CA: 2006. 1009893
    • CIR II Program: Crack Growth Testing of Fast Reactor Irradiated Type 304L Stainless Steel in BWR Environments, EPRI, Palo Alto, CA: 2006. 1009893
  • 21
    • 51649115160 scopus 로고    scopus 로고
    • An Interim Review of the Cooperative Irradiation-Assisted Stress Corrosion Cracking Research (CIR) Program, EPRI, Palo Alto, CA: 2006. 1013381
    • An Interim Review of the Cooperative Irradiation-Assisted Stress Corrosion Cracking Research (CIR) Program, EPRI, Palo Alto, CA: 2006. 1013381
  • 23
    • 12444331003 scopus 로고    scopus 로고
    • The Relationship Between Hardness and Yield Stress in Irradiated Austenitic and Ferritic Steels
    • Busby J.T., Hash, M.C., and Was G.S., "The Relationship Between Hardness and Yield Stress in Irradiated Austenitic and Ferritic Steels," J. Nucl. Mater. 336 (2005) 267-278.
    • (2005) J. Nucl. Mater , vol.336 , pp. 267-278
    • Busby, J.T.1    Hash, M.C.2    Was, G.S.3


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.