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Volumn 63, Issue 1, 2007, Pages 19-45

Stress corrosion cracking behavior of alloys in aggressive nuclear reactor core environments

Author keywords

Irradiated microstructure; Irridation assisted stress corrosion cracking; Light water reactors; Radiation induced segregation; Radiolysis; Water chemistry

Indexed keywords

CREEP; DEFORMATION; IRRADIATION; LIGHT WATER REACTORS; METALLOGRAPHIC MICROSTRUCTURE; RADIOLYSIS; STRESS CORROSION CRACKING;

EID: 34248221990     PISSN: 00109312     EISSN: None     Source Type: Journal    
DOI: 10.5006/1.3278331     Document Type: Conference Paper
Times cited : (122)

References (148)
  • 2
    • 0002585992 scopus 로고
    • Corrosion in Nuclear Systems: Environmentally Assisted Cracking in Light Water Reactors
    • eds. P. Marcus, J. Oudar New York, NY: Marcel Dekker
    • F.P. Ford, P.L. Andresen, "Corrosion in Nuclear Systems: Environmentally Assisted Cracking in Light Water Reactors," in Corrosion Mechanisms, eds. P. Marcus, J. Oudar (New York, NY: Marcel Dekker, 1994), p. 501-546.
    • (1994) Corrosion Mechanisms , pp. 501-546
    • Ford, F.P.1    Andresen, P.L.2
  • 3
    • 34248222856 scopus 로고    scopus 로고
    • F.P. Ford, P.L. Andresen, Development and Use of a Predictive Model of Crack Propagation in 304/316L, A533B/A508 and Inconel 600/182 Alloys in 288°C Water, Proc. 3rd Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, eds. G.J. Theus, J.R. Weeks (New York, NY: The Metallurgical Society of The American Institute of Mining, Metallurgical, and Petroleum Engineers [AIME], 1988), p. 789.
    • F.P. Ford, P.L. Andresen, "Development and Use of a Predictive Model of Crack Propagation in 304/316L, A533B/A508 and Inconel 600/182 Alloys in 288°C Water," Proc. 3rd Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, eds. G.J. Theus, J.R. Weeks (New York, NY: The Metallurgical Society of The American Institute of Mining, Metallurgical, and Petroleum Engineers [AIME], 1988), p. 789.
  • 5
    • 0027814032 scopus 로고    scopus 로고
    • M. Kodama, R. Katsura, J. Morisawa, S. Nishimura, S. Suzuki, K. Asano, K. Fukuya, K. Nakata, IASCC Susceptibility of Austenitic Stainless Steels Irradiated to High Neutron Fluences, Proc. 6th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, eds. R.E. Gold, E.P. Simonen (Warrendale, PA: The Minerals, Metals, and Materials Society, 1993), p. 583.
    • M. Kodama, R. Katsura, J. Morisawa, S. Nishimura, S. Suzuki, K. Asano, K. Fukuya, K. Nakata, "IASCC Susceptibility of Austenitic Stainless Steels Irradiated to High Neutron Fluences," Proc. 6th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, eds. R.E. Gold, E.P. Simonen (Warrendale, PA: The Minerals, Metals, and Materials Society, 1993), p. 583.
  • 9
    • 0002898590 scopus 로고
    • Irradiation-Assisted Stress Corrosion Cracking
    • ed. R.H. Jones Materials Park, OH: ASM International
    • P.L. Andresen, "Irradiation-Assisted Stress Corrosion Cracking," in Stress Corrosion Cracking: Materials Performance and Evaluation, ed. R.H. Jones (Materials Park, OH: ASM International, 1992), p. 181-210.
    • (1992) Stress Corrosion Cracking: Materials Performance and Evaluation , pp. 181-210
    • Andresen, P.L.1
  • 14
    • 34248185742 scopus 로고
    • Intergranular Stress Corrosion Cracking and Grain Boundary Composition of Fe-Ni-Cr Alloys
    • eds. R.W. Staehle, J. Hochmann, R.D. McCright, J.E. Slatern, held June, Houston, TX: NACE
    • R.L. Cowan, G.M Gordon, "Intergranular Stress Corrosion Cracking and Grain Boundary Composition of Fe-Ni-Cr Alloys," in Stress Corrosion Cracking and Hydrogen Embrittlement of Iron-Base Alloys, eds. R.W. Staehle, J. Hochmann, R.D. McCright, J.E. Slatern, held June 1973 (Houston, TX: NACE, 1977), p. 1,063-1,065.
    • (1973) Stress Corrosion Cracking and Hydrogen Embrittlement of Iron-Base Alloys
    • Cowan, R.L.1    Gordon, G.M.2
  • 24
    • 85040268608 scopus 로고
    • Investigation of Stress Corrosion in Clad Fuel Elements and Fuel Performance in the Connecticut Yankee Reactor
    • November
    • V. Pasupathi, R.W. Klingensmith, "Investigation of Stress Corrosion in Clad Fuel Elements and Fuel Performance in the Connecticut Yankee Reactor," Electric Power Research Institute (EPRI), NP-2119, November 1981.
    • (1981) Electric Power Research Institute (EPRI), NP-2119
    • Pasupathi, V.1    Klingensmith, R.W.2
  • 30
    • 1642338236 scopus 로고    scopus 로고
    • Analysis of the Partition - Reinforcement Connecting Screws of the Tihange 1 Power Plant
    • Paris, France: French Society of Nuclear Energy, in French
    • P.A. Heuze, O. Goltrant, R. Cauvin, "Analysis of the Partition - Reinforcement Connecting Screws of the Tihange 1 Power Plant," Proc. Int. Symp. Fontevraud IV (Paris, France: French Society of Nuclear Energy, 1998), p. 195 (in French).
    • (1998) Proc. Int. Symp. Fontevraud , vol.4 , pp. 195
    • Heuze, P.A.1    Goltrant, O.2    Cauvin, R.3
  • 31
    • 1942510519 scopus 로고    scopus 로고
    • P.M. Scott, M.-C. Meunier, D. Deydier, S. Silvestre, A. Trenty, An Analysis of Baffle/Former Bolt Cracking in French PWRs, ASTM STP 1401, Environmentally Assisted Cracking: Predictive Methods for Risk Assessment and Evaluation of Materials, Equipment and Structures, ed. R.D. Kane (West Conshohocken, PA: ASTM International, 2000), p. 210-223.
    • P.M. Scott, M.-C. Meunier, D. Deydier, S. Silvestre, A. Trenty, "An Analysis of Baffle/Former Bolt Cracking in French PWRs," ASTM STP 1401, Environmentally Assisted Cracking: Predictive Methods for Risk Assessment and Evaluation of Materials, Equipment and Structures, ed. R.D. Kane (West Conshohocken, PA: ASTM International, 2000), p. 210-223.
  • 37
    • 34248143633 scopus 로고    scopus 로고
    • P.L. Andresen, T.P. Diaz, S. Hettiarachchi, Resolving Electrocatalytic SCC Mitigation Issues in High-Temperature Water, CORROSION/2004, paper no. 04668 (Houston, TX: NACE, 2004).
    • P.L. Andresen, T.P. Diaz, S. Hettiarachchi, "Resolving Electrocatalytic SCC Mitigation Issues in High-Temperature Water," CORROSION/2004, paper no. 04668 (Houston, TX: NACE, 2004).
  • 41
    • 34248213302 scopus 로고    scopus 로고
    • P.L. Andresen, M.M. Morra, W.R. Catlin, Effects of Yield Strength, Corrosion Potential, Composition and Stress Intensity Factor in SCC of Stainless Steels, CORROSION/2004, paper no. 04678 (Houston, TX: NACE, 2004).
    • P.L. Andresen, M.M. Morra, W.R. Catlin, "Effects of Yield Strength, Corrosion Potential, Composition and Stress Intensity Factor in SCC of Stainless Steels," CORROSION/2004, paper no. 04678 (Houston, TX: NACE, 2004).
  • 45
    • 85031249507 scopus 로고    scopus 로고
    • T.M. Angeliu, P.L. Andresen, E. Hall, J.A. Sutliff, S. Sitzman, M. Yamamoto, J. Kuniya, Strain and Microstructure Characterization of Austenitic Stainless Steel Weld HAZs, CORROSION/2000, paper no. 186 (Houston, TX: NACE, 2000).
    • T.M. Angeliu, P.L. Andresen, E. Hall, J.A. Sutliff, S. Sitzman, M. Yamamoto, J. Kuniya, "Strain and Microstructure Characterization of Austenitic Stainless Steel Weld HAZs," CORROSION/2000, paper no. 186 (Houston, TX: NACE, 2000).
  • 52
    • 34248159694 scopus 로고    scopus 로고
    • Proc. Water Chemistry of Nuclear Reactor Systems, no. 5, held October 23-27 (London, U.K.: British Nuclear Energy Society, 1989).
    • Proc. Water Chemistry of Nuclear Reactor Systems, no. 5, held October 23-27 (London, U.K.: British Nuclear Energy Society, 1989).
  • 53
    • 0026102988 scopus 로고
    • Response of Electrochemical Sensors to Ionizing Radiation in High-Temperature Aqueous Environments
    • paper no. 501 Houston, TX: NACE
    • D.F. Taylor, "Response of Electrochemical Sensors to Ionizing Radiation in High-Temperature Aqueous Environments," CORROSION/90, paper no. 501 (Houston, TX: NACE, 1990).
    • (1990) CORROSION/90
    • Taylor, D.F.1
  • 55
    • 34248137671 scopus 로고    scopus 로고
    • R.A. Head, M.E. Indig, P.L. Andresen, Measurement of In-Core and Recirculation System Responses to Hydrogen Water Chemistry at Nine Mile Point Unit 1 BWR, Electric Power Research Institute (EPRI) Contract RP2680-5, Final Report, 1989.
    • R.A. Head, M.E. Indig, P.L. Andresen, "Measurement of In-Core and Recirculation System Responses to Hydrogen Water Chemistry at Nine Mile Point Unit 1 BWR," Electric Power Research Institute (EPRI) Contract RP2680-5, Final Report, 1989.
  • 57
    • 34248140362 scopus 로고    scopus 로고
    • D.F. Taylor, C.A. Caramihas, High-Temperature Aqueous Crevice Corrosion in Alloy 600 and 304L Stainless Steel, in Localized Crack Chemistry and Mechanics of Environmentally Assisted Cracking (New York, NY: The American Institute of Mining, Metallurgy, and Petroleum Engineers [AIME], 1983).
    • D.F. Taylor, C.A. Caramihas, "High-Temperature Aqueous Crevice Corrosion in Alloy 600 and 304L Stainless Steel," in Localized Crack Chemistry and Mechanics of Environmentally Assisted Cracking (New York, NY: The American Institute of Mining, Metallurgy, and Petroleum Engineers [AIME], 1983).
  • 58
    • 34248156931 scopus 로고    scopus 로고
    • P. Combrade, M. Foucault, G. Slama, About the Crack Tip Environment Chemistry in Pressure Vessel Steel Exposed to Primary PWR Coolant, Proc. Atomic Energy Agency Specialists Meeting on Subcritical Crack Growth, NUREG/CP0067, 2 held May 1985 (Sendai, Japan: Nuclear Regulatory Agency, 1985), p. 201-218.
    • P. Combrade, M. Foucault, G. Slama, "About the Crack Tip Environment Chemistry in Pressure Vessel Steel Exposed to Primary PWR Coolant," Proc. Atomic Energy Agency Specialists Meeting on Subcritical Crack Growth, NUREG/CP0067, vol. 2 held May 1985 (Sendai, Japan: Nuclear Regulatory Agency, 1985), p. 201-218.
  • 59
    • 34248179754 scopus 로고    scopus 로고
    • G. Gabetta, G. Buzzanaca, Measurement of Corrosion Potential Inside and Outside Growing Crack During Environmental Fatigue Tests, Proc. Atomic Energy Agency Specialists Meeting on Subcritical Crack Growth, NUREG/CP0067, 2, held May (Sendai, Japan: Nuclear Regulatory Agency, 1985), p. 219-230.
    • G. Gabetta, G. Buzzanaca, "Measurement of Corrosion Potential Inside and Outside Growing Crack During Environmental Fatigue Tests," Proc. Atomic Energy Agency Specialists Meeting on Subcritical Crack Growth, NUREG/CP0067, vol. 2, held May (Sendai, Japan: Nuclear Regulatory Agency, 1985), p. 219-230.
  • 60
    • 0002872042 scopus 로고
    • Behavior of Short Cracks in Stainless Steels and Inconels in 288°C Water
    • paper no. 495 Houston, TX: NACE
    • P.L. Andresen, I.P. Vasatis, F.P. Ford, "Behavior of Short Cracks in Stainless Steels and Inconels in 288°C Water," CORROSION/90, paper no. 495 (Houston, TX: NACE, 1990).
    • (1990) CORROSION/90
    • Andresen, P.L.1    Vasatis, I.P.2    Ford, F.P.3
  • 62
    • 0642297790 scopus 로고
    • Modeling of Irradiation Effects on Stress Corrosion Crack Growth Rates
    • paper no. 497 Houston, TX: NACE
    • P.L. Andresen, F.P. Ford, "Modeling of Irradiation Effects on Stress Corrosion Crack Growth Rates," CORROSION/89, paper no. 497 (Houston, TX: NACE, 1989).
    • (1989) CORROSION/89
    • Andresen, P.L.1    Ford, F.P.2
  • 63
    • 34248158388 scopus 로고    scopus 로고
    • P.L. Andresen, F.P. Ford, Modeling of Irradiation Effects on Stress Corrosion Crack Growth in Laboratory and Field Data, Int. Cooperative Group on Irradiation-Assisted Stress Corrosion Cracking (ICG-IASCC) minutes, April 1989.
    • P.L. Andresen, F.P. Ford, "Modeling of Irradiation Effects on Stress Corrosion Crack Growth in Laboratory and Field Data," Int. Cooperative Group on Irradiation-Assisted Stress Corrosion Cracking (ICG-IASCC) minutes, April 1989.
  • 67
    • 0020254166 scopus 로고    scopus 로고
    • N.Q. Lam, A. Kumar, H. Wiedersich, Kinetics of Radiation-Induced Segregation in Ternary Alloys, Proc. Effects of Radiation on Materials, 11th Conf. ASTM STP 782, eds. H.R. Brager, J.S. Perrin (West Conshohocken, PA: ASTM International, 1982), p. 985.
    • N.Q. Lam, A. Kumar, H. Wiedersich, "Kinetics of Radiation-Induced Segregation in Ternary Alloys," Proc. Effects of Radiation on Materials, 11th Conf. ASTM STP 782, eds. H.R. Brager, J.S. Perrin (West Conshohocken, PA: ASTM International, 1982), p. 985.
  • 68
    • 34248164173 scopus 로고    scopus 로고
    • J.M. Perks, A.D. Marwick, C.A. English, Fundamental Aspects of Radiation-Induced Segregation in Fe-Cr-Ni Alloys, Proc. Radiation-Induced Sensitisation of Stainless Steels, ed. D.I. Norris (Berkeley, Gloucestershire, U.K.: Central Electricity Generating Board, Berkeley Nuclear Labs, 1987), p. 15.
    • J.M. Perks, A.D. Marwick, C.A. English, "Fundamental Aspects of Radiation-Induced Segregation in Fe-Cr-Ni Alloys," Proc. Radiation-Induced Sensitisation of Stainless Steels, ed. D.I. Norris (Berkeley, Gloucestershire, U.K.: Central Electricity Generating Board, Berkeley Nuclear Labs, 1987), p. 15.
  • 71
    • 0032591964 scopus 로고    scopus 로고
    • Microchemistry of Proton-Irradiated Austenitic Alloys Under Conditions Relevant to LWR Core Components
    • Warrendale, PA: Materials Research Society
    • G.S. Was, T.R. Allen, J.T. Busby, J. Gan, D. Damcott, D. Carter, M. Atzmon, "Microchemistry of Proton-Irradiated Austenitic Alloys Under Conditions Relevant to LWR Core Components," Proc. Mater. Res. Soc., vol. 540 (Warrendale, PA: Materials Research Society, 1999), p. 421-432.
    • (1999) Proc. Mater. Res. Soc , vol.540 , pp. 421-432
    • Was, G.S.1    Allen, T.R.2    Busby, J.T.3    Gan, J.4    Damcott, D.5    Carter, D.6    Atzmon, M.7
  • 73
    • 34248163154 scopus 로고    scopus 로고
    • Pacific Northwest National Laboratory, private communication
    • E. Simonen, Pacific Northwest National Laboratory, private communication, 2001.
    • (2001)
    • Simonen, E.1
  • 75
    • 34248225081 scopus 로고    scopus 로고
    • K. Asano, K. Fukuya, K. Nakata, M. Kodama, Changes in Grain Boundary Composition Induced by Neutron Irradiation on Austenitic Stainless Steels, Proc. 5th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, eds. D. Cubicciotti, E.P. Simonen, R.E. Gold (LaGrange, IL: American Nuclear Society, 1992), p. 838.
    • K. Asano, K. Fukuya, K. Nakata, M. Kodama, "Changes in Grain Boundary Composition Induced by Neutron Irradiation on Austenitic Stainless Steels," Proc. 5th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, eds. D. Cubicciotti, E.P. Simonen, R.E. Gold (LaGrange, IL: American Nuclear Society, 1992), p. 838.
  • 76
    • 34248152387 scopus 로고    scopus 로고
    • A. Jacobs, Effects of Low-Temperature Annealing on the Microstructure and Grain Boundary Chemistry of Irradiated Type 304SS and Correlations with IASCC Resistance, Proc. 7th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (Houston, TX: NACE, 1995), p. 1,021.
    • A. Jacobs, "Effects of Low-Temperature Annealing on the Microstructure and Grain Boundary Chemistry of Irradiated Type 304SS and Correlations with IASCC Resistance," Proc. 7th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (Houston, TX: NACE, 1995), p. 1,021.
  • 77
    • 0027887735 scopus 로고    scopus 로고
    • A.J. Jacobs, G.P. Wozadlo, K. Nakata, S. Kasahara, T. Okada T. S. Kawano, S. Suzuki, The Correlation of Grain Boundary Composition in Irradiated Stainless Steel with IASCC Resistance, Proc. 6th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, eds. R.E. Gold, E.P. Simonen (Warrendale, PA: The Minerals, Metals, and Materials Society, 1993), p. 597.
    • A.J. Jacobs, G.P. Wozadlo, K. Nakata, S. Kasahara, T. Okada T. S. Kawano, S. Suzuki, "The Correlation of Grain Boundary Composition in Irradiated Stainless Steel with IASCC Resistance," Proc. 6th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, eds. R.E. Gold, E.P. Simonen (Warrendale, PA: The Minerals, Metals, and Materials Society, 1993), p. 597.
  • 84
    • 0032591962 scopus 로고    scopus 로고
    • Origin and Influence of Pre-Existing Segregation on Radiation Induced Segregation in Austenitic Stainless Steel
    • Warrendale, PA: Materials Research Society
    • E.A. Kenik, M.A. Miller, M. Thavander, J.T. Busby, G.S. Was, "Origin and Influence of Pre-Existing Segregation on Radiation Induced Segregation in Austenitic Stainless Steel," Proc. Materials Research Society, vol. 54 (Warrendale, PA: Materials Research Society, 1999), p. 445.
    • (1999) Proc. Materials Research Society , vol.54 , pp. 445
    • Kenik, E.A.1    Miller, M.A.2    Thavander, M.3    Busby, J.T.4    Was, G.S.5
  • 90
    • 0027887734 scopus 로고    scopus 로고
    • S. Dumbill, M. Hanks, Strategies for the Moderation of Chromium Depletion at Grain Boundaries in Irradiated Steels, Proc. 6th Int. Symp. Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, eds. R.E. Gold, E.P. Simonen (Warrendale, PA: The Minerals, Metals, and Materials Society, 1993), p. 521.
    • S. Dumbill, M. Hanks, "Strategies for the Moderation of Chromium Depletion at Grain Boundaries in Irradiated Steels," Proc. 6th Int. Symp. Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, eds. R.E. Gold, E.P. Simonen (Warrendale, PA: The Minerals, Metals, and Materials Society, 1993), p. 521.
  • 91
    • 34248177040 scopus 로고    scopus 로고
    • J.L. Nelson, P.L. Andresen, Review of Current Research and Understanding of Irradiation-Assisted Stress Corrosion Cracking, Proc. 5th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, eds. D. Cubicciotti, E.P. Simonen, R.E. Gold (La Grange Park, IL: American Nuclear Society, 1992), p. 10.
    • J.L. Nelson, P.L. Andresen, "Review of Current Research and Understanding of Irradiation-Assisted Stress Corrosion Cracking," Proc. 5th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, eds. D. Cubicciotti, E.P. Simonen, R.E. Gold (La Grange Park, IL: American Nuclear Society, 1992), p. 10.
  • 98
    • 32944463309 scopus 로고    scopus 로고
    • J.I. Cole, T.R. Allen, G.S. Was, E.A. Kenik, The Influence of Pre-Irradiation Heat Treatments on Thermal Non-Equilibrium and Radiation-Induced Segregation Behavior in Model Austenitic Stainless Steel Alloys, Effects of Radiation on Materials: 21st Int. Symp., ASTM STP, eds. M.L. Grossbeck, T.R. Allen, R.G. Lott, A.S. Kumar (West Conshohocken: ASTM International, 2004), p. 540-552.
    • J.I. Cole, T.R. Allen, G.S. Was, E.A. Kenik, "The Influence of Pre-Irradiation Heat Treatments on Thermal Non-Equilibrium and Radiation-Induced Segregation Behavior in Model Austenitic Stainless Steel Alloys," Effects of Radiation on Materials: 21st Int. Symp., ASTM STP, eds. M.L. Grossbeck, T.R. Allen, R.G. Lott, A.S. Kumar (West Conshohocken: ASTM International, 2004), p. 540-552.
  • 104
    • 34248156930 scopus 로고    scopus 로고
    • T. Yonezawa, K. Fujimoto, T. Iwamura, S. Nishida, ASTM 1401, Improvement of IASCC Resistance for Austenitic Stainless Steels in PWR Environment, Environmentally Assisted Cracking: Predictive Methods for Risk Assessment and Evaluation of Materials, Equipment, and Structures, ed. R.D. Kane (West Conshohocken, PA. ASTM International, 2000), p. 224.
    • T. Yonezawa, K. Fujimoto, T. Iwamura, S. Nishida, ASTM 1401, "Improvement of IASCC Resistance for Austenitic Stainless Steels in PWR Environment," Environmentally Assisted Cracking: Predictive Methods for Risk Assessment and Evaluation of Materials, Equipment, and Structures, ed. R.D. Kane (West Conshohocken, PA. ASTM International, 2000), p. 224.
  • 105
    • 0033489292 scopus 로고    scopus 로고
    • T. Yonezawa, T. Iwamura, K. Fujimoto, K. Ajiki, Optimized Chemical Composition and Heat Treatment Conditions of 316 CW and High-Chromium Austenitic Stainless Steels for PWR Baffle Bolts, Proc. 9th Int. Conf. Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (Warrendale, PA: The Minerals, Metals, and Materials Society, 1999), p. 1,015.
    • T. Yonezawa, T. Iwamura, K. Fujimoto, K. Ajiki, "Optimized Chemical Composition and Heat Treatment Conditions of 316 CW and High-Chromium Austenitic Stainless Steels for PWR Baffle Bolts," Proc. 9th Int. Conf. Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (Warrendale, PA: The Minerals, Metals, and Materials Society, 1999), p. 1,015.
  • 114
    • 0030402460 scopus 로고    scopus 로고
    • R. Stoller, JOM 12 (1996): p. 23.
    • (1996) JOM , vol.12 , pp. 23
    • Stoller, R.1
  • 117
    • 84860210389 scopus 로고    scopus 로고
    • Effect of Single Solute Additions on Radiation-Induced Segregation and Microstructure of Model Austenitic Alloys
    • in press
    • J.T. Busby, E.A. Kenik, G.S. Was, "Effect of Single Solute Additions on Radiation-Induced Segregation and Microstructure of Model Austenitic Alloys," J. Nucl. Mater., in press.
    • J. Nucl. Mater
    • Busby, J.T.1    Kenik, E.A.2    Was, G.S.3
  • 120
    • 12444304295 scopus 로고    scopus 로고
    • The Studsvik MAT 1 Experiment, R2 Irradiations and Post-Irradiation Tensile Test
    • STUDSVIK/NS-90/13, 1990
    • U. Bergenlid, Y. Haag, K. Pettersson. "The Studsvik MAT 1 Experiment, R2 Irradiations and Post-Irradiation Tensile Test," Studsvik Report STUDSVIK/NS-90/13, 1990.
    • Studsvik Report
    • Bergenlid, U.1    Haag, Y.2    Pettersson, K.3
  • 121
    • 34248152890 scopus 로고    scopus 로고
    • M. Kodama, S. Suzuki, K. Nakata, S. Nishimura, K. Jukuya, T. Kato, Y. Tanaka, S. Shima, Mechanical Properties of Various Kinds of Irradiated Austenitic Stainless Steels, Proc. 8th Int. Symp. on Environment Degradation of Materials in Nuclear Power Systems - Water Reactor, eds. A.R. McIlree, S.M. Bruemmer (La Grange Park, IL: American Nuclear Society, 1997), p. 831.
    • M. Kodama, S. Suzuki, K. Nakata, S. Nishimura, K. Jukuya, T. Kato, Y. Tanaka, S. Shima, "Mechanical Properties of Various Kinds of Irradiated Austenitic Stainless Steels," Proc. 8th Int. Symp. on Environment Degradation of Materials in Nuclear Power Systems - Water Reactor, eds. A.R. McIlree, S.M. Bruemmer (La Grange Park, IL: American Nuclear Society, 1997), p. 831.
  • 123
    • 34248220152 scopus 로고    scopus 로고
    • A. Jenssen, ABB Atom, written communication, 1998.
    • A. Jenssen, ABB Atom, written communication, 1998.
  • 125
  • 126
    • 0027850881 scopus 로고    scopus 로고
    • S.M. Bruemmer, J. Cole, R. Carter, G.S. Was, Radiation Hardening Effects on Localized Deformation and Stress Corrosion Cracking of Stainless Steels, Proc. 6th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, eds. R.E. Gold, E.P. Simonen (Warrendale, PA: The Minerals, Metals, and Materials Society, 1993), p. 537.
    • S.M. Bruemmer, J. Cole, R. Carter, G.S. Was, "Radiation Hardening Effects on Localized Deformation and Stress Corrosion Cracking of Stainless Steels," Proc. 6th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, eds. R.E. Gold, E.P. Simonen (Warrendale, PA: The Minerals, Metals, and Materials Society, 1993), p. 537.
  • 127
    • 0038803179 scopus 로고
    • Irradiation Strengthening and Embrittlement
    • eds. N.L. Peterson, S.D. Harkness Materials Park, OH: ASM International
    • E.E. Bloom, "Irradiation Strengthening and Embrittlement," in Radiation Damage in Metals, eds. N.L. Peterson, S.D. Harkness (Materials Park, OH: ASM International, 1975), p. 295.
    • (1975) Radiation Damage in Metals , pp. 295
    • Bloom, E.E.1
  • 128
    • 0033489127 scopus 로고    scopus 로고
    • M.O. Speidel, R. Magdowski, Stress Corrosion Cracking of Stabilized Austenitic Stainless Steels in Various Types of Nuclear Power Plants, Proc. 9th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systemr - Water Reactors, eds. F.P. Ford, S.M. Bruemmer, G.S. Was (Warrendale, PA: Metallurgical Society of The American Institute of Mining, Metallurgical, and Petroleum Engineers [AIME], 1999), p. 325.
    • M.O. Speidel, R. Magdowski, "Stress Corrosion Cracking of Stabilized Austenitic Stainless Steels in Various Types of Nuclear Power Plants," Proc. 9th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systemr - Water Reactors, eds. F.P. Ford, S.M. Bruemmer, G.S. Was (Warrendale, PA: Metallurgical Society of The American Institute of Mining, Metallurgical, and Petroleum Engineers [AIME], 1999), p. 325.
  • 130
    • 32944471246 scopus 로고    scopus 로고
    • M.C. Hash, L.M. Wang, J.T. Busby, G.S. Was, The Effect of Hardening Source in Proton Irradiation-Assisted Stress Corrosion Cracking of Cold-Worked Type 304 Stainless Steel, Effects of Radiation on Materials: 21st Int. Symp., eds. M. R. Grossbeck, T.R. Allen, R.G. Lott, A.S. Kumar, ASTM STP1447 (West Conshohocken, PA: ASTM International, 2004), p. 92-104.
    • M.C. Hash, L.M. Wang, J.T. Busby, G.S. Was, "The Effect of Hardening Source in Proton Irradiation-Assisted Stress Corrosion Cracking of Cold-Worked Type 304 Stainless Steel," Effects of Radiation on Materials: 21st Int. Symp., eds. M. R. Grossbeck, T.R. Allen, R.G. Lott, A.S. Kumar, ASTM STP1447 (West Conshohocken, PA: ASTM International, 2004), p. 92-104.
  • 131
    • 0028272644 scopus 로고    scopus 로고
    • M. Kodama, K. Fukuya, H. Kayano, Influence of Impurities and Alloying Elements on IASCC in Neutron-Irradiated Austenitic Stainless Steels, Proc. 16th Int. Symp. on Radiation Effects on Materials, eds. A.S. Kumar, D.S. Gelles, R.K. Nanstad, E.A. Little, ASTM STP 1175 West Conshohocken, PA: ASTM International, 1994, p. 889.
    • M. Kodama, K. Fukuya, H. Kayano, "Influence of Impurities and Alloying Elements on IASCC in Neutron-Irradiated Austenitic Stainless Steels," Proc. 16th Int. Symp. on Radiation Effects on Materials, eds. A.S. Kumar, D.S. Gelles, R.K. Nanstad, E.A. Little, ASTM STP 1175 West Conshohocken, PA: ASTM International, 1994), p. 889.
  • 132
    • 0002074942 scopus 로고    scopus 로고
    • The Importance of Molybdenum on Irradiation-Assisted Stress Corrosion Cracking in Austenitic Stainless Steels
    • paper no. 101 Houston, TX: NACE International
    • A. Jenssen, L. Ljungberg, J. Walmsley, S. Fisher, "The Importance of Molybdenum on Irradiation-Assisted Stress Corrosion Cracking in Austenitic Stainless Steels," CORROSION/96, paper no. 101 (Houston, TX: NACE International, 1996).
    • (1996) CORROSION/96
    • Jenssen, A.1    Ljungberg, L.2    Walmsley, J.3    Fisher, S.4
  • 133
    • 0006341997 scopus 로고
    • A Study of Radiation-Induced Sensitization in 20/25/Nb Steel by Compositional Profile Measurements at Grain Boundaries
    • paper no. 52 London, U.K, BNES
    • D.I.R. Norris, C. Baker, C. Taylor, J.M. Titchmarsh, "A Study of Radiation-Induced Sensitization in 20/25/Nb Steel by Compositional Profile Measurements at Grain Boundaries," in Materials for Nuclear Reactor Core Applications, paper no. 52 (London, U.K.: BNES, 1987).
    • (1987) Materials for Nuclear Reactor Core Applications
    • Norris, D.I.R.1    Baker, C.2    Taylor, C.3    Titchmarsh, J.M.4
  • 135
    • 0003128433 scopus 로고
    • The Role of Metallurgical Variables in Hydrogen-Assisted Environmental Fracture
    • eds. R.W. Staehle, M.G. Fontana, New York, NY: Plenum Press
    • A.W. Thompson, I.M. Bernstein, "The Role of Metallurgical Variables in Hydrogen-Assisted Environmental Fracture," in Advances in Corrosion Science and Technology, eds. R.W. Staehle, M.G. Fontana, vol. 7 (New York, NY: Plenum Press, 1980), p. 53.
    • (1980) Advances in Corrosion Science and Technology , vol.7 , pp. 53
    • Thompson, A.W.1    Bernstein, I.M.2
  • 142
    • 33144459425 scopus 로고    scopus 로고
    • J.T. Busby, M.M. Sowa, G.S. Was, The Role of Fine Defect Clusters in Irradiation-Assisted Stress Corrosion Cracking of Proton-Irradiated 304 Stainless Steel, Effects of Radiation on Material: 21st Int. Symp., eds. M.R. Grossbeck, T.R. Allen, R.G. Lott, A.S.Kumar, ASTM STP (West Conshohocken, PA: ASTM International, 2004), p. 78-91.
    • J.T. Busby, M.M. Sowa, G.S. Was, "The Role of Fine Defect Clusters in Irradiation-Assisted Stress Corrosion Cracking of Proton-Irradiated 304 Stainless Steel," Effects of Radiation on Material: 21st Int. Symp., eds. M.R. Grossbeck, T.R. Allen, R.G. Lott, A.S.Kumar, ASTM STP (West Conshohocken, PA: ASTM International, 2004), p. 78-91.
  • 143
    • 0033489337 scopus 로고    scopus 로고
    • L.E. Thomas, S.M. Bruemmer, Insights into Environmental Degradation Mechanisms from Analytical Transmission Electron Microscopy of SCC Cracks, Proc. 9th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, eds. F.P. Ford, S.M. Bruemmer, G.S. Was (Warrendale, PA: Metallurgical Society of The American Institute of Mining, Metallurgical, and Petroleum Engineers [AIME], 1999), p. 41.
    • L.E. Thomas, S.M. Bruemmer, "Insights into Environmental Degradation Mechanisms from Analytical Transmission Electron Microscopy of SCC Cracks," Proc. 9th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, eds. F.P. Ford, S.M. Bruemmer, G.S. Was (Warrendale, PA: Metallurgical Society of The American Institute of Mining, Metallurgical, and Petroleum Engineers [AIME], 1999), p. 41.
  • 144
    • 0028342195 scopus 로고    scopus 로고
    • J.C. Van Duysen, P. Todeschini, G. Zacharie, Effects of Neutron Irradiations at Temperatures Below 550°C on the Properties of Cold Worked 361 Stainless Steels: A Review, Effects of Radiation on Materials: 16th Int. Symp., ASTM STP1175 (West Conshohocken, PA: ASTM International, 1993), p. 747-776.
    • J.C. Van Duysen, P. Todeschini, G. Zacharie, "Effects of Neutron Irradiations at Temperatures Below 550°C on the Properties of Cold Worked 361 Stainless Steels: A Review," Effects of Radiation on Materials: 16th Int. Symp., ASTM STP1175 (West Conshohocken, PA: ASTM International, 1993), p. 747-776.
  • 145
    • 0017214185 scopus 로고    scopus 로고
    • J. P. Foster, Analysis of In-Reactor Stress Relaxation Using Irradiation Creep Models, Proc. Irradiation Effects on the Microstructure and Properties of Metals, ASTM STP611 (West Conshohocken, PA: ASTM International, 1976), p. 32.
    • J. P. Foster, "Analysis of In-Reactor Stress Relaxation Using Irradiation Creep Models," Proc. Irradiation Effects on the Microstructure and Properties of Metals, ASTM STP611 (West Conshohocken, PA: ASTM International, 1976), p. 32.


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