메뉴 건너뛰기




Volumn 29, Issue 1-2, 2011, Pages 7-49

Irradiation-assisted stress corrosion cracking

Author keywords

Boiling water reactors; Corrosion potential; Crack growth; Crack initiation; High temperature water; Localized deformation; Nickel base alloys; Nuclear materials; Pressuri zed water reactors; Radiation creep relaxation; Radiation effects; Radiation hardening; Radiation induced segregation (RIS); Radiolysis; Stainless steels; Stress corrosion cracking; Water chemistry

Indexed keywords

CORROSION POTENTIALS; CREEP RELAXATION; HIGH-TEMPERATURE WATER; LOCALIZED DEFORMATIONS; NICKEL BASE ALLOYS; NUCLEAR MATERIAL; RADIATION-INDUCED SEGREGATION; WATER CHEMISTRY; WATER REACTORS;

EID: 84860145736     PISSN: 03346005     EISSN: None     Source Type: Journal    
DOI: 10.1515/CORRREV.2011.020     Document Type: Article
Times cited : (74)

References (236)
  • 1
    • 0141537094 scopus 로고    scopus 로고
    • Grain boundary deformation-induced intergranular stress corrosion cracking of Ni-16Cr-9Fe in 360°C water
    • Alexandreanu B, Was GS. Grain boundary deformation-induced intergranular stress corrosion cracking of Ni-16Cr-9Fe in 360 degrees C water. Corrosion 2003; 59: 705 - 720. (Pubitemid 37118393)
    • (2003) Corrosion , vol.59 , Issue.8 , pp. 705-720
    • Alexandreanu, B.1    Was, G.S.2
  • 2
    • 0035961158 scopus 로고    scopus 로고
    • Combined effect of special grain boundaries and grain boundary carbides on IGSCC of Ni-16Cr-9Fe-xC alloys
    • DOI 10.1016/S0921-5093(00)01705-6, PII S0921509300017056
    • Alexandreanu B, Capell B, Was GS. Combined effect of special grain boundaries and grain boundary carbides on IGSCC of Ni-16Cr- 9Fe-xC alloys. Mater Sci Engin A 2001; 300: 94 - 104. (Pubitemid 32300311)
    • (2001) Materials Science and Engineering A , vol.300 , Issue.1-2 , pp. 94-104
    • Alexandreanu, B.1    Capell, B.2    Was, G.S.3
  • 3
    • 0032072553 scopus 로고    scopus 로고
    • On the mechanism of radiation-induced segregation in austenitic Fe-Cr-Ni alloys
    • PII S0022311598000105
    • Allen TR, Busby JT, Was GS, Kenik EA. On the mechanism of radiation- induced segregation in austenitic Fe-Cr-Ni alloys. J Nucl Mater 1998; 255: 44 - 58. (Pubitemid 128423625)
    • (1998) Journal of Nuclear Materials , vol.255 , Issue.1 , pp. 44-58
    • Allen, T.R.1    Busby, J.T.2    Was, G.S.3    Kenik, E.A.4
  • 5
    • 0027659271 scopus 로고
    • Effects of temperature on crack growth rate in sensitized type 304 stainless steel and alloy 600
    • Andresen PL Effects of temperature on crack growth rate in sensitized type 304 stainless steel and alloy 600 Corrosion 1993; 49: 714 - 725.
    • (1993) Corrosion , vol.49 , pp. 714-725
    • Andresen, P.L.1
  • 8
    • 2442519695 scopus 로고    scopus 로고
    • Conceptual similarities and common predictive approaches for SCC in high temperature water systems
    • NACE, Paper 96258
    • Andresen PL. Conceptual similarities and common predictive approaches for SCC in high temperature water systems. In: Corrosion/96. NACE, 1996: Paper 96258.
    • (1996) Corrosion/96
    • Andresen, P.L.1
  • 10
    • 7744234758 scopus 로고    scopus 로고
    • Similarity of cold work and radiation hardening in enhancing yield strength and SCC growth of stainless steel in hot water
    • Houston, TX: NACE, Paper No. 02509
    • Andresen PL. Similarity of cold work and radiation hardening in enhancing yield strength and SCC growth of stainless steel in hot water. In: Corrosion 2002. Houston, TX: NACE, 2002: Paper No. 02509.
    • (2002) Corrosion 2002
    • Andresen, P.L.1
  • 12
    • 84858226725 scopus 로고    scopus 로고
    • Critical processes to model in predicting SCC response in hot water
    • Houston, TX: NACE, Paper No. 05470
    • Andresen PL. Critical processes to model in predicting SCC response in hot water. In: Corrosion 2005. Houston, TX: NACE, 2005a: Paper No. 05470.
    • (2005) Corrosion 2005
    • Andresen, P.L.1
  • 13
    • 84860129868 scopus 로고    scopus 로고
    • Critical processes to model in predicting SCC response in hot water
    • Andresen PL. Critical processes to model in predicting SCC response in hot water. Power Plant Chemistry 2005b; 7: 541 - 560.
    • (2005) Power Plant Chemistry , vol.7 , pp. 541-560
    • Andresen, P.L.1
  • 14
    • 84860134599 scopus 로고    scopus 로고
    • Short crack response of alloy 182 in PWR primary water
    • Palo Alto, CA
    • Andresen PL. Short crack response of alloy 182 in PWR primary water. Report 1016545. Palo Alto, CA: EPRI, 2008a.
    • (2008) Report 1016545, EPRI
    • Andresen, P.L.1
  • 16
    • 84860115180 scopus 로고    scopus 로고
    • Stress corrosion cracking in austenitic stainless steels
    • Tipping PG, editor, Woodhead Publishing
    • Andresen PL. Stress corrosion cracking in austenitic stainless steels. In: Tipping PG, editor. Understanding and mitigating ageing in nuclear power plants. Woodhead Publishing, 2010a.
    • (2010) Understanding and Mitigating Ageing in Nuclear Power Plants
    • Andresen, P.L.1
  • 17
    • 84865453183 scopus 로고    scopus 로고
    • SCC of stainless steels in hot water
    • Avignon, France: SFEN
    • Andresen PL. SCC of stainless steels in hot water. In: Proc. Fontevraud 7. Avignon, France: SFEN, 2010b.
    • (2010) Proc. Fontevraud 7
    • Andresen, P.L.1
  • 18
    • 0024054216 scopus 로고
    • Life prediction by mechanistic modeling and system monitoring of environmental cracking of iron and nickel- alloys in aqueous systems
    • Andresen PL, Ford FP. Life prediction by mechanistic modeling and system monitoring of environmental cracking of iron and nickel- alloys in aqueous systems. Mat Sci Eng a-Struct 1988; 103: 167 - 184.
    • (1988) Mat Sci Eng A-Struct , vol.103 , pp. 167-184
    • Andresen, P.L.1    Ford, F.P.2
  • 20
    • 0642297790 scopus 로고
    • Modeling of irradiation effects on stress corrosion crack growth rates
    • Houston, TX: NACE, Paper No. 497
    • Andresen PL, Ford FP. Modeling of irradiation effects on stress corrosion crack growth rates. In: CORROSION/89. Houston, TX: NACE, 1989b: Paper No. 497.
    • (1989) CORROSION/89
    • Andresen, P.L.1    Ford, F.P.2
  • 21
    • 0027929646 scopus 로고
    • Fundamental modeling of environmental cracking for improved design and lifetime evaluation in BWRs
    • Andresen P, Ford F. Fundamental modeling of environmental cracking for improved design and lifetime evaluation in BWRs. Int J Pres Ves Pip 1994; 59: 61 - 70.
    • (1994) Int J Pres Ves Pip , vol.59 , pp. 61-70
    • Andresen, P.1    Ford, F.2
  • 23
    • 85034864908 scopus 로고    scopus 로고
    • Effects of Si on SCC of irradiated and unirradiated stainless steels and nickel alloys
    • Houston, TX: NACE, Paper No. 05591
    • Andresen PL, Morra MM. Effects of Si on SCC of irradiated and unirradiated stainless steels and nickel alloys. In: Corrosion 2005. Houston, TX: NACE, 2005a: Paper No. 05591.
    • (2005) Corrosion 2005
    • Andresen, P.L.1    Morra, M.M.2
  • 26
    • 51749094772 scopus 로고    scopus 로고
    • Effects of dK/da on SCC growth rates
    • Houston, TX: NACE, Paper No. 07488
    • Andresen PL, Morra MM. Effects of dK/da on SCC growth rates. In: Corrosion 2007. Houston, TX: NACE, 2007b: Paper No. 07488.
    • (2007) Corrosion 2007
    • Andresen, P.L.1    Morra, M.M.2
  • 27
    • 38049037442 scopus 로고    scopus 로고
    • Stress corrosion cracking of stainless steels and nickel alloys in high-temperature water
    • Andresen PL, Morra MM. Stress corrosion cracking of stainless steels and nickel alloys in high-temperature water. Corrosion 2008a; 64: 15 - 29.
    • (2008) Corrosion , vol.64 , pp. 15-29
    • Andresen, P.L.1    Morra, M.M.2
  • 28
    • 56149092825 scopus 로고    scopus 로고
    • IGSCC of non-sensitized stainless steels in high temperature water
    • Andresen PL, Morra MM. IGSCC of non-sensitized stainless steels in high temperature water. J Nucl Mater 2008b; 383: 97 - 111.
    • (2008) J Nucl Mater , vol.383 , pp. 97-111
    • Andresen, P.L.1    Morra, M.M.2
  • 29
    • 84865005220 scopus 로고    scopus 로고
    • SCC of unirradiated stainless steels and nickel alloys in hot water
    • Houston, TX: NACE
    • Andresen PL, Was GS. SCC of unirradiated stainless steels and nickel alloys in hot water. In: 17th International Corrosion Congress. Houston, TX: NACE, 2008.
    • (2008) 17th International Corrosion Congress
    • Andresen, P.L.1    Was, G.S.2
  • 32
    • 0002872042 scopus 로고
    • Behavior of short cracks in stainless steels and Inconels in 288 °C water
    • Houston, TX: NACE, Paper No. 495
    • Andresen PL, Vasatis IP, Ford FP. Behavior of short cracks in stainless steels and Inconels in 288 °Cwater. In: CORROSION/90. Houston, TX: NACE, 1990b: Paper No. 495.
    • (1990) CORROSION/90
    • Andresen, P.L.1    Vasatis, I.P.2    Ford, F.P.3
  • 36
    • 84860127562 scopus 로고    scopus 로고
    • Resolving electrocatalytic SCC mitigation issues in high temperature water
    • Houston, TX: NACE, Paper No. 04668
    • Andresen PL, Diaz TP, Hettiarachchi S. Resolving electrocatalytic SCC mitigation issues in high temperature water. In: Corrosion/2004. Houston, TX: NACE, 2004a: Paper No. 04668.
    • (2004) Corrosion/2004
    • Andresen, P.L.1    Diaz, T.P.2    Hettiarachchi, S.3
  • 37
    • 69249088720 scopus 로고    scopus 로고
    • Effects of yield strength, corrosion potential, composition and stress intensity factor in SCC of stainless steels
    • Houston, TX: NACE, Paper No. 04678
    • Andresen PL, Morra MM, Catlin WR. Effects of yield strength, corrosion potential, composition and stress intensity factor in SCC of stainless steels. In: Corrosion/2004. Houston, TX: NACE, 2004b: Paper No. 04678.
    • (2004) Corrosion/2004
    • Andresen, P.L.1    Morra, M.M.2    Catlin, W.R.3
  • 38
    • 84921437369 scopus 로고    scopus 로고
    • Effects of PWR primary water chemistry and deaerated water on SCC
    • Houston, TX: NACE, Paper No. 05592
    • Andresen PL, Emigh PW, Morra MM. Effects of PWR primary water chemistry and deaerated water on SCC. In: Corrosion 2005. Houston, TX: NACE, 2005: Paper No. 05592.
    • (2005) Corrosion 2005
    • Andresen, P.L.1    Emigh, P.W.2    Morra, M.M.3
  • 40
    • 70449535449 scopus 로고    scopus 로고
    • Microstructural and stress corrosion cracking characteristics of austenitic stainless steels containing silicon
    • Andresen PL, Chou PH, Morra MM, Nelson LJ, Rebak RB. Microstructural and stress corrosion cracking characteristics of austenitic stainless steels containing silicon. Metall Mater Trans A 2009; 40: 2824 - 2836.
    • (2009) Metall Mater Trans A , vol.40 , pp. 2824-2836
    • Andresen, P.L.1    Chou, P.H.2    Morra, M.M.3    Nelson, L.J.4    Rebak, R.B.5
  • 43
    • 34248188360 scopus 로고
    • Radiation effects on mechanical properties and microstructure of type-304 stainless steel
    • Armijo JS, Low JR, Wolff UE. Radiation effects on mechanical properties and microstructure of type-304 stainless steel. Nuc Appl 1965; 1: 462.
    • (1965) Nuc Appl , pp. 1-462
    • Armijo, J.S.1    Low, J.R.2    Wolff, U.E.3
  • 45
    • 0034540538 scopus 로고    scopus 로고
    • Effects of irradiation and testing temperature on tensile behaviour of stainless steels
    • DOI 10.1016/S0022-3115(00)00083-0
    • Bailat C, Almazouzi A, Baluc N, Schäublin R, Gröschel F, Victoria M. The effects of irradiation and testing temperature on tensile behaviour of stainless steels. J Nucl Mater 2000; 283 - 287: 446 - 450. (Pubitemid 32028868)
    • (2000) Journal of Nuclear Materials , vol.283-287 , Issue.PART I , pp. 446-450
    • Bailat, C.1    Almazouzi, A.2    Baluc, N.3    Schaublin, R.4    Groschel, F.5    Victoria, M.6
  • 47
    • 0038803179 scopus 로고
    • Irradiation strengthening and embrittlement
    • Materials Park, OH: ASM International
    • Bloom EE. Irradiation strengthening and embrittlement. In: Radiation damage in metals. Materials Park, OH: ASM International, 1975: 295.
    • (1975) Radiation Damage in Metals , vol.295
    • Bloom, E.E.1
  • 49
    • 0010660153 scopus 로고
    • Effects of BWR coolant chemistry on the propensity for igscc initiation and growth in creviced reactor internals components
    • New York, NY: The American Institute of Mining, Metallurgical, and Petroleum Engineers (AIME)
    • Brown KS, Gordon GM. Effects of BWR coolant chemistry on the propensity for IGSCC initiation and growth in creviced reactor internals components. In: Proc 3rd Int Conf on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors. New York, NY: The American Institute of Mining, Metallurgical, and Petroleum Engineers (AIME), 1988: 243 - 248.
    • (1988) Proc 3rd Int Conf on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors , pp. 243-248
    • Brown, K.S.1    Gordon, G.M.2
  • 52
    • 0028518339 scopus 로고
    • Microstructural and microchemical mechanisms controlling intergranular stress-corrosion cracking in light-water-reactor systems
    • Bruemmer SM, Was GS. microstructural and microchemical mechanisms controlling intergranular stress-corrosion cracking in light-water-reactor systems. J Nucl Mater 1994; 216: 348 - 363.
    • (1994) J Nucl Mater , vol.216 , pp. 348-363
    • Bruemmer, S.M.1    Was, G.S.2
  • 56
    • 0033338807 scopus 로고    scopus 로고
    • Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals
    • DOI 10.1016/S0022-3115(99)00075-6
    • Bruemmer SM, Simonen EP, Scott PM, Andresen PL, Was GS, Nelson JL. Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals. J Nucl Mater 1999; 274: 299 - 314. (Pubitemid 30507816)
    • (1999) Journal of Nuclear Materials , vol.274 , Issue.3 , 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
  • 57
    • 0017194685 scopus 로고
    • Water radiolysis and its effect upon in-reactor zircaloy corrosion
    • Burns WG, Moore PB. Water radiolysis and its effect upon in-reactor zircaloy corrosion. Radiation Effects and Defects in Solids 1976; 30: 233 - 242.
    • (1976) Radiation Effects and Defects in Solids , vol.30 , pp. 233-242
    • Burns, W.G.1    Moore, P.B.2
  • 58
  • 59
    • 84860210389 scopus 로고    scopus 로고
    • Effect of single solute additions on radiation induced segregation and microstructure of model austenitic alloys
    • in press
    • Busby JT, Kenik EA, Was GS. 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
  • 60
    • 0036532066 scopus 로고    scopus 로고
    • Isolating the effect of radiation-induced segregation in irradiation-assisted stress corrosion cracking of austenitic stainless steels
    • DOI 10.1016/S0022-3115(02)00719-5, PII S0022311502007195
    • Busby JT, Was GS, Kenik EA. Isolating the effect of radiation-induced segregation in irradiation-assisted stress corrosion cracking of austenitic stainless steels. J Nucl Mater 2002; 302: 20 - 40. (Pubitemid 34228484)
    • (2002) Journal of Nuclear Materials , vol.302 , Issue.1 , pp. 20-40
    • Busby, J.T.1    Was, G.S.2    Kenik, E.A.3
  • 61
    • 33144459425 scopus 로고    scopus 로고
    • The role of fine defect clusters in irradiation-assisted stress corrosion cracking of proton-irradiated 304 stainless steel
    • JAI11317, Effects of Radiation on Materials: 21st International Symposium
    • Busby JT, Sowa MM, Was GS. The role of fi ne defect clusters in irradiation assisted stress corrosion cracking of proton irradiated 304 stainless steel. In: Effects of Radiation on Material: 21st Int. Symp. (ASTM STP1447). West Conshohocken, PA: ASTM International, 2004: 78 - 91. (Pubitemid 43262425)
    • (2004) ASTM Special Technical Publication , Issue.1447 , pp. 78-91
    • Busby, J.T.1    Sowa, M.M.2    Was, G.S.3    Kenik, E.A.4
  • 62
    • 32144443180 scopus 로고    scopus 로고
    • Post-irradiation annealing of small defect clusters
    • DOI 10.1080/02678370412331320071, PII V728
    • Busby JT, Sowa MM, Was GS, Simonen EP. Post-irradiation annealing of small defect clusters. Philos Mag 2005; 85: 609 - 617. (Pubitemid 43203567)
    • (2005) Philosophical Magazine , vol.85 , Issue.SPEC. ISS. , pp. 609-617
    • Busby, J.T.1    Sowa, M.M.2    Was, G.S.3    Simonen, E.P.4
  • 66
    • 84860156316 scopus 로고    scopus 로고
    • Irradiation-assisted stress corrosion cracking of austenitic stainless steels in BWR environments
    • NUREG/CR-7018
    • Chen Y, Chopra OK, Gruber EE, Shack WJ. Irradiation-assisted stress corrosion cracking of austenitic stainless steels in BWR environments. Argonne Report ANL-09/17, NUREG/CR-7018. 2010.
    • (2010) Argonne Report ANL-09/17
    • Chen, Y.1    Chopra, O.K.2    Gruber, E.E.3    Shack, W.J.4
  • 67
    • 33745248771 scopus 로고
    • Corrosion aspects of iron austenitic stainless steel + Inconel in high temperature water
    • Cheng CF. Corrosion aspects of iron austenitic stainless steel + Inconel in high temperature water. Corrosion 1964; 20: 341.
    • (1964) Corrosion , pp. 20-341
    • Cheng, C.F.1
  • 68
    • 34248161740 scopus 로고
    • Intergranular corrosion cracking of type-304 stainless steel in water-cooled reactors
    • Cheng CF. Intergranular corrosion cracking of type-304 stainless steel in water-cooled reactors. React Technol 1970; 13: 310.
    • (1970) React Technol , pp. 13-310
    • Cheng, C.F.1
  • 69
    • 0016528764 scopus 로고
    • Intergranular stress-assisted corrosion cracking of austenitic alloys in water-cooled nuclear-reactors
    • Cheng CF. Intergranular stress-assisted corrosion cracking of austenitic alloys in water-cooled nuclear-reactors. J Nucl Mater 1975; 57: 11 - 33.
    • (1975) J Nucl Mater , vol.57 , pp. 11-33
    • Cheng, C.F.1
  • 70
    • 79951515444 scopus 로고    scopus 로고
    • A review of irradiation effects on LWR core internal materials-IASCC susceptibility and crack growth rates of austenitic stainless steels
    • Chopra OK, Rao AS. A review of irradiation effects on LWR core internal materials-IASCC susceptibility and crack growth rates of austenitic stainless steels. J Nucl Mater 2011; 409: 235 - 256.
    • (2011) J Nucl Mater , vol.409 , pp. 235-256
    • Chopra, O.K.1    Rao, A.S.2
  • 71
    • 84860210362 scopus 로고    scopus 로고
    • Crack growth rates and fracture toughness of irradiated austenitic stainless steels in bwr environments
    • NUREG/CR-6960
    • Chopra OK, Shack WJ. Crack growth rates and fracture toughness of irradiated austenitic stainless steels in bwr environments. Argonne Report ANL-06/58, NUREG/CR-6960. 2008.
    • (2008) Argonne Report ANL-06/58
    • Chopra, O.K.1    Shack, W.J.2
  • 72
    • 29144532821 scopus 로고    scopus 로고
    • Fracture toughness and crack growth rates of irradiated austenitic stainless steels
    • NUREG/CR-6826
    • Chopra OK, Gruber EE, Shack WJ. Fracture toughness and crack growth rates of irradiated austenitic stainless steels. Argonne Report ANL-03/22, NUREG/CR-6826. 2003.
    • (2003) Argonne Report ANL-03/22
    • Chopra, O.K.1    Gruber, E.E.2    Shack, W.J.3
  • 73
    • 84860210391 scopus 로고    scopus 로고
    • Crack growth rates of irradiated austenitic stainless steel weld heat affected zone in bwr environments
    • NUREG/CR-6891
    • Chopra OK, Alexandreanu B, Gruber EE, Daum RS, Shack WJ. Crack growth rates of irradiated austenitic stainless steel weld heat affected zone in BWR environments. Argonne Report ANL- 04/20, NUREG/CR-6891. 2006.
    • (2006) Argonne Report ANL- 04/20
    • Chopra, O.K.1    Alexandreanu, B.2    Gruber, E.E.3    Daum, R.S.4    Shack, W.J.5
  • 76
    • 84860161549 scopus 로고    scopus 로고
    • The infl uence of preirradiation heat treatments on thermal non-equilibrium and radiation-induced segregation behavior in model austenitic stainless steel alloys
    • American Society for Testing and Materials, West Conshohocken
    • Cole JI, Allen TR, Was GS, Kenik EA. The infl uence of preirradiation heat treatments on thermal non-equilibrium and radiation-induced segregation behavior in model austenitic stainless steel alloys. In: Effects of Radiation on Materials: 21st International Symposium. American Society for Testing and Materials, West Conshohocken, 2004.
    • (2004) Effects of Radiation on Materials: 21st International Symposium
    • Cole, J.I.1    Allen, T.R.2    Was, G.S.3    Kenik, E.A.4
  • 78
    • 0032034404 scopus 로고    scopus 로고
    • Oxide-induced initiation of stress corrosion cracking in irradiated stainless steel
    • Cookson J, Was GS. Oxide-induced initiation of stress corrosion cracking in irradiated stainless steel. Corrosion 1998; 54: 299 - 312.
    • (1998) Corrosion , vol.54 , pp. 299-312
    • Cookson, J.1    Was, G.S.2
  • 79
    • 34248185742 scopus 로고
    • Intergranular stress corrosion cracking and grain boundary composition of fe-ni-cr alloys
    • Firminy, France: NACE, Houston
    • Cowan RL, Gordon GM. Intergranular stress corrosion cracking and grain boundary composition of Fe-Ni-Cr alloys. In: Stress corrosion cracking and hydrogen embrittlement of iron-base alloys. Firminy, France: NACE, Houston, 1977: 1063 - 1065.
    • (1977) Stress Corrosion Cracking and Hydrogen Embrittlement of Iron-base Alloys. , pp. 1063-1065
    • Cowan, R.L.1    Gordon, G.M.2
  • 80
    • 84860185542 scopus 로고    scopus 로고
    • Evaluation of fundamental linkage among stress corrosion cracking (SCC) Phenomena
    • Palo Alto, CA
    • Davis RB, Andresen PL. Evaluation of fundamental linkage among stress corrosion cracking (SCC) Phenomena. Report 1007378. Palo Alto, CA: EPRI, 2002.
    • (2002) Report 1007378, EPRI
    • Davis, R.B.1    Andresen, P.L.2
  • 81
    • 84860165895 scopus 로고    scopus 로고
    • BWRVIP-99-A: Crack growth rates in irradiated stainless steels in BWR internal components
    • Palo Alto, CA
    • Davis RB, Horn RM, Andresen PL, Nelson JL. BWRVIP-99-A: crack growth rates in irradiated stainless steels in BWR internal components. Report 1016566. Palo Alto, CA: EPRI, 2008.
    • (2008) Report 1016566, EPRI
    • Davis, R.B.1    Horn, R.M.2    Andresen, P.L.3    Nelson, J.L.4
  • 82
  • 88
    • 0242417835 scopus 로고    scopus 로고
    • Evolution of fi ne-scale defects in stainless steels neutron-irradiated at 275 degrees c
    • Edwards DJ, Simonen EP, Bruemmer SM. Evolution of fi ne-scale defects in stainless steels neutron-irradiated at 275 degrees C. J Nucl Mater 2003a; 317: 13 - 31.
    • (2003) J Nucl Mater , vol.317 , pp. 13-31
    • Edwards, D.J.1    Simonen, E.P.2    Bruemmer, S.M.3
  • 89
    • 0242585793 scopus 로고    scopus 로고
    • Infl uence of irradiation temperature and dose gradients on the microstructural evolution in neutron-irradiated 316SS
    • Edwards DJ, Simonen EP, Garner FA, Greenwood LR, Oliver BM, Bruemmer SM. Infl uence of irradiation temperature and dose gradients on the microstructural evolution in neutron-irradiated 316SS. J Nucl Mater 2003b; 317: 32 - 45.
    • (2003) J Nucl Mater , vol.317 , pp. 32-45
    • Edwards, D.J.1    Simonen, E.P.2    Garner, F.A.3    Greenwood, L.R.4    Oliver, B.M.5    Bruemmer, S.M.6
  • 91
    • 84860115206 scopus 로고    scopus 로고
    • Crack growth testing of tailored alloys from Boris 6 and 7 irradiations
    • Palo Alto, CA
    • Ernestova M, Burda J. Crack growth testing of tailored alloys from Boris 6 and 7 irradiations. Report No. 1021235. Palo Alto, CA: EPRI, 2009.
    • (2009) Report No. 1021235, EPRI
    • Ernestova, M.1    Burda, J.2
  • 93
    • 0038489354 scopus 로고    scopus 로고
    • Mapping flow localization processes in deformation of irradiated reactor structural alloys
    • Farrell K, Byun TS, Hashimoto N. Mapping flow localization processes in deformation of irradiated reactor structural alloys. Report ORNL/TM-2002/66. ORNL, 2002.
    • (2002) Report ORNL/TM-2002/66, ORNL
    • Farrell, K.1    Byun, T.S.2    Hashimoto, N.3
  • 94
    • 0002139532 scopus 로고
    • Development and use of a predictive model of crack propagation in 304/316L, A533B/A508 and Inconel 600/182 Alloys in 288 °C water
    • New York, NY: The Metallurgical Society of The American Institute of Mining, Metallurgical, and Petroleum Engineers (AIME)
    • Ford FP, Andresen PL. Development and use of a predictive model of crack propagation in 304/316L, A533B/A508 and Inconel 600/182 Alloys in 288 °C water. In: Proc 3rd Int Symp on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors. New York, NY: The Metallurgical Society of The American Institute of Mining, Metallurgical, and Petroleum Engineers (AIME), 1988: 789.
    • (1988) Proc 3rd Int Symp on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors , vol.789
    • Ford, F.P.1    Andresen, P.L.2
  • 95
    • 0002585992 scopus 로고
    • Corrosion in nuclear systems: Environmentally assisted cracking in light water reactors
    • New York, NY: Marcel Dekker
    • Ford FP, Andresen PL. Corrosion in nuclear systems: environmentally assisted cracking in light water reactors. In: Corrosion mechanisms. New York, NY: Marcel Dekker, 1994: 501 - 546.
    • (1994) Corrosion Mechanisms , pp. 501-546
    • Ford, F.P.1    Andresen, P.L.2
  • 98
    • 84860143482 scopus 로고    scopus 로고
    • Materials reliability program: Hot cell testing of baffl e/former bolts removed from two lead PWR plants (MRP-51)
    • Palo Alto, CA
    • Forsyth DR. Materials reliability program: hot cell testing of baffl e/former bolts removed from two lead PWR plants (MRP-51). Report 1003069. Palo Alto, CA: EPRI, 2001.
    • (2001) Report 1003069, EPRI
    • Forsyth, D.R.1
  • 99
    • 0041380836 scopus 로고    scopus 로고
    • The influence of oversized solute additions on radiation-induced changes and post-irradiation intergranular stress corrosion cracking behavior in high-purity 316 stainless steels
    • Fournier L, Sencer BH, Was GS, Simonen EP, Bruemmer SM. The infl uence of oversized solute additions on radiation-induced changes and post-irradiation intergranular stress corrosion cracking behavior in high-purity 316 stainless steels. J Nucl Mater 2003; 321: 192 - 209.
    • (2003) J Nucl Mater , vol.321 , pp. 192-209
    • Fournier, L.1    Sencer, B.H.2    Was, G.S.3    Simonen, E.P.4    Bruemmer, S.M.5
  • 101
    • 13244287839 scopus 로고    scopus 로고
    • Separation of microstructural and microchemical effects in irradiation assisted stress corrosion cracking using post-irradiation annealing
    • Fukuya K, Nakano M, Fujii K, Torimaru T, Kitsunai Y. Separation of microstructural and microchemical effects in irradiation assisted stress corrosion cracking using post-irradiation annealing. J Nucl Sci Technol 2004; 41: 1218.
    • (2004) J Nucl Sci Technol , vol.41 , pp. 1218
    • Fukuya, K.1    Nakano, M.2    Fujii, K.3    Torimaru, T.4    Kitsunai, Y.5
  • 102
    • 3142645248 scopus 로고    scopus 로고
    • Role of radiationinduced grain boundary segregation in irradiation assisted stress corrosion cracking
    • Fukuya K, Nakano M, Fujii K, Torimaru T. Role of radiationinduced grain boundary segregation in irradiation assisted stress corrosion cracking. J Nucl Sci Technol 2004a; 41: 594 - 600.
    • (2004) J Nucl Sci Technol , vol.41 , pp. 594-600
    • Fukuya, K.1    Nakano, M.2    Fujii, K.3    Torimaru, T.4
  • 103
    • 4043051010 scopus 로고    scopus 로고
    • IASCC susceptibility and slow tensile properties of highly-irradiated 316 stainless steels
    • Fukuya K, Nakano M, Fujii K, Torimaru T. IASCC susceptibility and slow tensile properties of highly-irradiated 316 stainless steels. J Nucl Sci Technol 2004b; 41: 673 - 681.
    • (2004) J Nucl Sci Technol , vol.41 , pp. 673-681
    • Fukuya, K.1    Nakano, M.2    Fujii, K.3    Torimaru, T.4
  • 104
    • 0013002558 scopus 로고
    • Measurement of corrosion potential inside and outside growing crack during environmental fatigue tests
    • Sendai, Japan: Nuclear Regulatory Agency
    • Gabetta G, Buzzanaca G. Measurement of corrosion potential inside and outside growing crack during environmental fatigue tests. In: Proc Atomic Energy Agency Specialists Meeting on Subcritical Crack Growth, NUREG/CP0067, Vol. 2. Sendai, Japan: Nuclear Regulatory Agency, 1985: 219 - 230.
    • (1985) Proc Atomic Energy Agency Specialists Meeting on Subcritical Crack Growth, NUREG/CP0067 , vol.2 , pp. 219-230
    • Gabetta, G.1    Buzzanaca, G.2
  • 106
    • 0002708148 scopus 로고
    • Elastic plastic fi elds in steady crack growth in a strain-hardening material
    • Gao YC, Hwang KC. Elastic plastic fi elds in steady crack growth in a strain-hardening material. In: 5th Int Conf on Fracture. 1981: 669 - 682.
    • (1981) 5th Int Conf on Fracture , pp. 669-682
    • Gao, Y.C.1    Hwang, K.C.2
  • 107
    • 0020734544 scopus 로고
    • The asymptotic near-tip solution for mode III crack in steady growth in power hardening media
    • Gao YC, Zhang XT, Hwang KC. The asymptotic near-tip solution for mode III crack in steady growth in power hardening media. Int J Fract 1983; 21: 301 - 331.
    • (1983) Int J Fract , vol.21 , pp. 301-331
    • Gao, Y.C.1    Zhang, X.T.2    Hwang, K.C.3
  • 108
    • 0027680518 scopus 로고
    • Evolution of microstructure in face-centered cubic metals during irradiation
    • Garner FA. Evolution of microstructure in face-centered cubic metals during irradiation. J Nucl Mater 1993; 205: 98 - 117.
    • (1993) J Nucl Mater , vol.205 , pp. 98-117
    • Garner, F.A.1
  • 110
    • 0012911059 scopus 로고
    • Deformability of austenitic stainless steels and nickel-based alloys in the core of a boiling and a pressurized water reactor
    • LaGrange Park, IL: American Nuclear Society (ANS)
    • Garzarolli F, Alter D, Dewes P. Deformability of austenitic stainless steels and nickel-based alloys in the core of a boiling and a pressurized water reactor. In: Proc 2nd Int Symp on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors. LaGrange Park, IL: American Nuclear Society (ANS), 1986: 131 - 138.
    • (1986) Proc 2nd Int Symp on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors , pp. 131-138
    • Garzarolli, F.1    Alter, D.2    Dewes, P.3
  • 111
    • 0012957899 scopus 로고
    • Deformability of austenitic stainless steels and nickel-based alloys in the core of a boiling and a pressurized water reactor
    • New York, NY: The American Institute of Mining, Metallurgical, and Petroleum Engineers (AIME)
    • Garzarolli F, Alter D, Dewes P, Nelson JL. Deformability of austenitic stainless steels and nickel-based alloys in the core of a boiling and a pressurized water reactor. In: Proc 3rd Int Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors. New York, NY: The American Institute of Mining, Metallurgical, and Petroleum Engineers (AIME), 1988: 657 - 664.
    • (1988) Proc 3rd Int Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors , pp. 657-664
    • Garzarolli, F.1    Alter, D.2    Dewes, P.3    Nelson, J.L.4
  • 113
    • 84860161534 scopus 로고
    • Hydrogen water chemistry for BWR, Task 27 - materials and environmental monitoring within the duane Arnold BWR
    • Palo Alto, CA
    • Gordon BM. Hydrogen water chemistry for BWR, Task 27 - materials and environmental monitoring within the duane Arnold BWR. Contract RP1930-1. Palo Alto, CA: EPRI, 1983.
    • (1983) Contract RP1930-1, EPRI
    • Gordon, B.M.1
  • 115
    • 64649087606 scopus 로고    scopus 로고
    • Effects of oversized solutes on radiation-induced segregation in austenitic stainless steels
    • Hackett MJ, Busby JT, Miller MK, Was GS. Effects of oversized solutes on radiation-induced segregation in austenitic stainless steels. J Nucl Mater 2009a; 389: 265 - 278.
    • (2009) J Nucl Mater , vol.389 , pp. 265-278
    • Hackett, M.J.1    Busby, J.T.2    Miller, M.K.3    Was, G.S.4
  • 116
    • 64649085798 scopus 로고    scopus 로고
    • Modeling solute-vacancy trapping at oversized solutes and its effect on radiation-induced segregation in fe-cr-ni alloys
    • Hackett MJ, Najafabadi R, Was GS. Modeling solute-vacancy trapping at oversized solutes and its effect on radiation-induced segregation in Fe-Cr-Ni alloys. J Nucl Mater 2009b; 389: 279 - 287.
    • (2009) J Nucl Mater , vol.389 , pp. 279-287
    • Hackett, M.J.1    Najafabadi, R.2    Was, G.S.3
  • 118
    • 32944471246 scopus 로고    scopus 로고
    • 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 International Symposium
    • Hash MC, Wang LM, Busby JT, Was GS. The effect of hardening source in proton irradiation assisted stress corrosion cracking of cold worked type 304 stainless steel. In: Effects of Radiation on Materials: 21st Int. Symp. (ASTM STP1447). West Conshohocken, PA: ASTM International, 2004: 92 - 104. (Pubitemid 43257653)
    • (2004) ASTM Special Technical Publication , Issue.1447 , pp. 92-104
    • Hash, M.C.1    Busby, J.T.2    Was, G.S.3
  • 119
    • 84860185600 scopus 로고
    • Measurement of in-core and recirculation system responses to hydrogen water chemistry at nine mile point unit 1 BWR
    • Palo Alto
    • Head RA, Indig ME, Andresen PL. Measurement of in-core and recirculation system responses to hydrogen water chemistry at nine mile point unit 1 BWR. Contract RP2680-5 (Final Report). Palo Alto: EPRI, 1989.
    • (1989) Contract RP2680-5 (Final Report), EPRI
    • Head, R.A.1    Indig, M.E.2    Andresen, P.L.3
  • 120
    • 0032024103 scopus 로고    scopus 로고
    • Role of carbon in the deformation and fracture of Ni-16Cr-9Fe alloys in 360 °C water
    • Hertzberg J, Was GS. Role of carbon in the deformation and fracture of Ni-16Cr-9Fe alloys in.360 °C water Metall Trans A 1998; 29A: 1035 - 1046.
    • (1998) Metall Trans A , vol.29 A , pp. 1035-1046
    • Hertzberg, J.1    Was, G.S.2
  • 122
    • 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]
    • Heuze PA, Goltrant O, Cauvin R. Analysis of the partition - reinforcement connecting screws of the Tihange 1 power plant. In: Proc Int Symp Fontevraud IV. Paris, France: French Society of Nuclear Energy, 1998: 195 [in French].
    • (1998) Proc Int Symp Fontevraud IV , vol.195
    • Heuze, P.A.1    Goltrant, O.2    Cauvin, R.3
  • 124
    • 84860156312 scopus 로고    scopus 로고
    • BWRVIP-232: Highly irradiated stainless steel crack growth program on general electric control rod blade materials
    • Palo Alto, CA
    • Horn R. BWRVIP-232: highly irradiated stainless steel crack growth program on general electric control rod blade materials. Report 1019078. Palo Alto, CA: EPRI, 2009.
    • (2009) Report 1019078, EPRI
    • Horn, R.1
  • 125
    • 0000801486 scopus 로고    scopus 로고
    • Experience and assessment of stress corrosion cracking in L-grade stainless steel BWR internals
    • PII S0029549397001313
    • Horn RM, Gordon GM, Ford FP, Cowan RL. Experience and assessment of stress corrosion cracking in L-grade stainless steel BWR internals. Nucl Eng Des 1997; 174: 313 - 325. (Pubitemid 127432199)
    • (1997) Nuclear Engineering and Design , vol.174 , Issue.3 , pp. 313-325
    • Horn, R.M.1    Gordon, G.M.2    Ford, F.P.3    Cowan, R.L.4
  • 126
    • 0030382173 scopus 로고    scopus 로고
    • Post-irradiation annealing effects on microstructure and helium bubbles in neutron irradiated type 304 stainless steel
    • DOI 10.1016/S0022-3115(96)00465-5, PII S0022311596004655
    • Ishiyama Y, Kodama M, Yokota N, Asano K, Kato T, Fukuya K. Post-irradiation annealing effects on microstructure and helium bubbles in neutron irradiated type 304 stainless steel. J Nucl Mater 1996; 239: 90 - 94. (Pubitemid 126365963)
    • (1996) Journal of Nuclear Materials , vol.239 , Issue.1-3 , pp. 90-94
    • Ishiyama, Y.1    Kodama, M.2    Yokota, N.3    Asano, K.4    Kato, T.5    Fukuya, K.6
  • 127
    • 0343913335 scopus 로고
    • Effects of low temperature annealing on the microstructure and grain boundary chemistry of irradiated type 304ss and correlations with IASCC resistance
    • Houston, TX: NACE
    • Jacobs A. Effects of low temperature annealing on the microstructure and grain boundary chemistry of irradiated type 304SS and correlations with IASCC resistance. In: Proc 7th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors. Houston, TX: NACE, 1995: 1021.
    • (1995) Proc 7th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors , pp. 1021
    • Jacobs, A.1
  • 133
    • 0029389377 scopus 로고
    • Low-temperature annealing-A process to mitigate irradiation-assisted stress-corrosion cracking
    • Jacobs AJ, Wozadlo GP, Gordon GM. Low-temperature annealing-a process to mitigate irradiation-assisted stress-corrosion cracking. Corrosion 1995; 51: 731 - 737.
    • (1995) Corrosion , vol.51 , pp. 731-737
    • Jacobs, A.J.1    Wozadlo, G.P.2    Gordon, G.M.3
  • 136
    • 84860115942 scopus 로고    scopus 로고
    • Crack growth rates of irradiated commercial stainless steels in BWR and PWR environments
    • Palo Alto, CA
    • Jenssen A, Stjarnsater J. Crack growth rates of irradiated commercial stainless steels in BWR and PWR environments. Report 1019028. Palo Alto, CA: EPRI, 2009.
    • (2009) Report 1019028, EPRI
    • Jenssen, A.1    Stjarnsater, J.2
  • 137
    • 0002074942 scopus 로고    scopus 로고
    • The importance of molybdenum on irradiation assisted stress corrosion cracking in austenitic stainless steels
    • Houston, TX: NACE, Paper No. 101
    • Jenssen A, Ljungberg L, Walmsley J, Fisher S. The importance of molybdenum on irradiation assisted stress corrosion cracking in austenitic stainless steels. In: Corrosion/96. Houston, TX: NACE, 1996: Paper No. 101.
    • (1996) Corrosion/96
    • Jenssen, A.1    Ljungberg, L.2    Walmsley, J.3    Fisher, S.4
  • 138
    • 0002074942 scopus 로고    scopus 로고
    • Importance of molybdenum on irradiation-assisted stress corrosion cracking in austenitic stainless steels
    • Jenssen A, Ljungberg LG, Walmsley J, Fisher S. Importance of molybdenum on irradiation-assisted stress corrosion cracking in austenitic stainless steels. Corrosion 1998; 54: 48 - 60.
    • (1998) Corrosion , Issue.54 , pp. 48-60
    • Jenssen, A.1    Ljungberg, L.G.2    Walmsley, J.3    Fisher, S.4
  • 140
    • 84860156314 scopus 로고    scopus 로고
    • CIR II program: Crack growth testing of fast reactor irradiated type 304L stainless steel in BWR environments
    • Palo Alto, CA
    • Jenssen A, Sundberg J, Konig M. CIR II program: crack growth testing of fast reactor irradiated type 304L stainless steel in BWR environments. Report 1014976. Palo Alto, CA: EPRI, 2007.
    • (2007) Report 1014976, EPRI
    • Jenssen, A.1    Sundberg, J.2    Konig, M.3
  • 141
    • 84860161539 scopus 로고    scopus 로고
    • BWRVIP-221: Crack growth in high fl uence BWR materials-Phase 1: Crack growth rate testing of types 304L and 316L at doses ranging from 3.5 to 13 dpa
    • Palo Alto, CA
    • Jenssen A, Stjarnsater J, Torimaru T, Kitsunai Y. BWRVIP-221: crack growth in high fl uence BWR materials-Phase 1: crack growth rate testing of types 304L and 316L at doses ranging from 3.5 to 13 dpa. Report 1019079. Palo Alto, CA: EPRI, 2009.
    • (2009) Report 1019079, EPRI
    • Jenssen, A.1    Stjarnsater, J.2    Torimaru, T.3    Kitsunai, Y.4
  • 142
    • 78349308521 scopus 로고    scopus 로고
    • The role of irradiated microstructure in the localized deformation of austenitic stainless steels
    • Jiao Z, Was GS. The role of irradiated microstructure in the localized deformation of austenitic stainless steels. J Nucl Mater 2010; 407: 34 - 43.
    • (2010) J Nucl Mater , vol.407 , pp. 34-43
    • Jiao, Z.1    Was, G.S.2
  • 143
    • 79251593835 scopus 로고    scopus 로고
    • Impact of localized deformation on IASCC in austenitic stainless steels
    • Jiao Z, Was GS. Impact of localized deformation on IASCC in austenitic stainless steels. J Nucl Mater 2011a; 408: 246 - 256.
    • (2011) J Nucl Mater , vol.408 , pp. 246-256
    • Jiao, Z.1    Was, G.S.2
  • 144
    • 78650737344 scopus 로고    scopus 로고
    • Novel features of radiation-induced segregation and radiation-induced precipitation in austenitic stainless steels
    • Jiao Z, Was GS. Novel features of radiation-induced segregation and radiation-induced precipitation in austenitic stainless steels. Acta Mate 2011b; 59: 1220 - 1238.
    • (2011) Acta Mate , vol.59 , pp. 1220-1238
    • Jiao, Z.1    Was, G.S.2
  • 148
    • 84860210379 scopus 로고    scopus 로고
    • Final Report on IFA-586/IFA-605: Effects of water chemistry on the in-pile crack growth behaviour of double cantilever beam specimens
    • Karlsen TM. Final Report on IFA-586/IFA-605: effects of water chemistry on the in-pile crack growth behaviour of double cantilever beam specimens. OECD Halden Reactor Project, HWR- 473. 1996.
    • (1996) OECD Halden Reactor Project, HWR-473
    • Karlsen, T.M.1
  • 149
    • 84860156304 scopus 로고    scopus 로고
    • TEM characterization of irradiated CW316 and SA304 stainless steels
    • Karlsen W. TEM characterization of irradiated CW316 and SA304 stainless steels. VTT Report VTT-R-00801-09. 2009.
    • (2009) VTT Report VTT-R-00801-09
    • Karlsen, W.1
  • 150
    • 78649373067 scopus 로고    scopus 로고
    • Final report on the in-pile crack growth behaviour of irradiated compact tension specimens in ifa-639
    • Karlsen TM, Horvath A. Final report on the in-pile crack growth behaviour of irradiated compact tension specimens in IFA-639. OECD Halden Reactor Project, HWR-770. 2004.
    • (2004) OECD Halden Reactor Project, HWR-770
    • Karlsen, T.M.1    Horvath, A.2
  • 151
    • 84860156306 scopus 로고    scopus 로고
    • FEG-STEM Study of 12 dpa Barseback 304L and 20 dpa and 30 dpa Chooz A 304SS
    • Karlsen W, Aaltonen P. FEG-STEM Study of 12 dpa Barseback 304L and 20 dpa and 30 dpa Chooz A 304SS. VTT Report VTT-R- 01215-07. 2007.
    • (2007) VTT Report VTT-R- 01215-07
    • Karlsen, W.1    Aaltonen, P.2
  • 155
    • 0027109059 scopus 로고
    • Grain boundary segregation under electron irradiation in austenitic stainless steels modified with oversized elements
    • DOI 10.1016/0022-3115(92)90529-T
    • Kato T, Takahashi H, Izumiya M. Grain-boundary segregation under electron-irradiation in austenitic stainless-steels modifi ed with oversized elements. J Nucl Mater 1992; 189: 167 - 174. (Pubitemid 23603733)
    • (1992) Journal of Nuclear Materials , vol.189 , Issue.2 , pp. 167-174
    • Kato Takahiko1    Takahashi Heishichiro2    Izumiya Masakiyo3
  • 157
    • 0026867843 scopus 로고
    • Radiation-induced segregation in irradiated type-304 stainless-steels
    • Kenik EA. Radiation-induced segregation in irradiated type-304 stainless-steels. J Nucl Mater 1992; 187: 239 - 246.
    • (1992) J Nucl Mater , vol.187 , pp. 239-246
    • Kenik, E.A.1
  • 158
    • 0028272644 scopus 로고
    • Infl uence of impurities and alloying elements on IASCC in neutron irradiated austenitic stainless steels
    • West Conshohocken, PA: ASTM International
    • Kodama M, Fukuya K, Kayano H. Infl uence of impurities and alloying elements on IASCC in neutron irradiated austenitic stainless steels. In: Proc 16th Int Symp on Radiation Effects on Materials (ASTM STP 1175). West Conshohocken, PA: ASTM International, 1994: 889.
    • (1994) Proc 16th Int Symp on Radiation Effects on Materials (ASTM STP 1175) , vol.889
    • Kodama, M.1    Fukuya, K.2    Kayano, H.3
  • 162
    • 3142558571 scopus 로고    scopus 로고
    • Effects of impurities on environmentally assisted crack growth of solution-annealed austenitic steels in primary water at 325 degrees C
    • Li GF, Kaneshima Y, Shoji T. Effects of impurities on environmentally assisted crack growth of solution-annealed austenitic steels in primary water at 325 degrees C. Corrosion 2000; 56: 460 - 469.
    • (2000) Corrosion , vol.56 , pp. 460-469
    • Li, G.F.1    Kaneshima, Y.2    Shoji, T.3
  • 164
    • 0002471466 scopus 로고
    • A Phenomenological investigation of in-reactor cracking of type-304 stainless-steel control rod cladding
    • Manahan MP, Kohli R, Santucci J, Sipush P. A Phenomenological investigation of in-reactor cracking of type-304 stainless-steel control rod cladding. Nucl Eng Des 1989; 113: 297 - 321.
    • (1989) Nucl Eng des , vol.113 , pp. 297-321
    • Manahan, M.P.1    Kohli, R.2    Santucci, J.3    Sipush, P.4
  • 165
    • 84860161765 scopus 로고    scopus 로고
    • CIR II program: description of the Boris 6 and 7 experiments in the BOR-60 fast breeder reactor
    • Palo Alto, CA
    • Massoud JP, Dubuisson P, Scott P, Chamardine VK. CIR II program: description of the Boris 6 and 7 experiments in the BOR-60 fast breeder reactor. Report 1011787. Palo Alto, CA: EPRI, 2005.
    • (2005) Report 1011787, EPRI
    • Massoud, J.P.1    Dubuisson, P.2    Scott, P.3    Chamardine, V.K.4
  • 166
    • 0027677314 scopus 로고
    • Overview of microstructural evolution in neutronirradiated austenitic stainless-steels
    • Maziasz PJ. Overview of microstructural evolution in neutronirradiated austenitic stainless-steels. J Nucl Mater 1993; 205: 118 - 145.
    • (1993) J Nucl Mater , vol.205 , pp. 118-145
    • Maziasz, P.J.1
  • 167
    • 0023560392 scopus 로고
    • Microstructural evolution in annealed austenitic steels during netron irradiation
    • Maziasz PJ, McHargue CJ. Microstructural evolution in annealed austenitic steels during neutron-irradiation. Int Mater Rev 1987; 32: 190 - 219. (Pubitemid 18578489)
    • (1987) International Materials Reviews , vol.32 , Issue.4 , pp. 190-219
    • Maziasz, P.J.1    McHargue, C.J.2
  • 168
    • 0030262185 scopus 로고    scopus 로고
    • Effect of minor elements on irradiation assisted stress corrosion cracking of model austenitic stainless steels
    • PII S0022311596002553
    • Miwa Y, Tsukada T, Jitsukawa S, Kita S, Hamada S, Matsui Y, Shindo M. Effect of minor elements on irradiation assisted stress corrosion cracking of model austenitic stainless steels. J Nucl Mater 1996: 1393 - 1396. (Pubitemid 126686675)
    • (1996) Journal of Nuclear Materials , vol.233-237 , Issue.PART II , pp. 1393-1396
    • Miwa, Y.1    Tsukada, T.2    Jitsukawa, S.3    Kita, S.4    Hamada, S.5    Matsui, Y.6    Shindo, M.7
  • 170
    • 0008268170 scopus 로고
    • Effects of neutron irradiation on corrosion and segregation behavior in austenitic stainless steels
    • Nakahigashi S, Kodama M, Fukuya K, Nishimura S, Yamamoto S, Saito K, Saito T. Effects of neutron irradiation on corrosion and segregation behavior in austenitic stainless steels. J Nucl Mater 1992; 179 - 181: 1061 - 1064.
    • (1992) J Nucl Mater , vol.179 , Issue.181 , pp. 1061-1064
    • Nakahigashi, S.1    Kodama, M.2    Fukuya, K.3    Nishimura, S.4    Yamamoto, S.5    Saito, K.6    Saito, T.7
  • 175
    • 0006341997 scopus 로고
    • A study of radiation induced sensitization in 20/25/Nb steel by compositional profi le measurements at grain boundaries
    • London, UK: BNES, Paper No. 52
    • Norris DIR, Baker C, Taylor C, Titchmarsh JM. A study of radiation induced sensitization in 20/25/Nb steel by compositional profi le measurements at grain boundaries. In: Materials for nuclear reactor core applications. London, UK: BNES, 1987a: Paper No. 52.
    • (1987) Materials for Nuclear Reactor Core Applications
    • Norris, D.I.R.1    Baker, C.2    Taylor, C.3    Titchmarsh, J.M.4
  • 177
    • 0002654073 scopus 로고
    • Intergranular stress corrosion cracking in steam generator tubing, testing of alloy 690 and alloy 600 tubes
    • Warrendale, PA: New York, NY: The American Institute of Mining, Metallurgical, and Petroleum Engineers (AIME)
    • Norring K, Engstrom J, Norberg P. Intergranular stress corrosion cracking in steam generator tubing, testing of alloy 690 and alloy 600 tubes. In: Proc 3rd Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors. Warrendale, PA: New York, NY: The American Institute of Mining, Metallurgical, and Petroleum Engineers (AIME), 1988: 587 - 593.
    • (1988) Proc 3rd Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors , pp. 587-593
    • Norring, K.1    Engstrom, J.2    Norberg, P.3
  • 178
    • 0018503777 scopus 로고
    • Radiation-induced segregation in binary and ternary alloys
    • Okamoto PR, Rehn LE. Radiation-induced segregation in binary and ternary alloys. J Nucl Mater 1979; 83: 2 - 23. (Pubitemid 9475774)
    • (1979) J Nucl Mater , vol.83 , Issue.1 , pp. 2-23
    • Okamoto, P.R.1    Rehn, L.E.2
  • 179
    • 0016104262 scopus 로고
    • Segregation of alloying elements to free surfaces during irradiation
    • Okamoto PR, Wiedersich H. Segregation of alloying elements to free surfaces during irradiation. J Nucl Mater 1974; 53: 336 - 345.
    • (1974) J Nucl Mater , vol.53 , pp. 336-345
    • Okamoto, P.R.1    Wiedersich, H.2
  • 182
    • 49549089744 scopus 로고    scopus 로고
    • EBSD Characterization of the deformation behavior of alloy 182 weld metal
    • Othon M, Morra M. EBSD Characterization of the deformation behavior of alloy 182 weld metal. Microsc Microanal 2008; 14(Suppl. S2): 934 - 935.
    • (2008) Microsc Microanal , vol.14 , Issue.S2 , pp. 934-935
    • Othon, M.1    Morra, M.2
  • 188
    • 0006308001 scopus 로고
    • Fundamental aspects of radiation induced segregation in Fe-Cr-Nialloys
    • Berkeley, Gloucestershire, UK: Central Electricity Generating Board, Berkeley Nuclear Labs
    • Perks JM, Marwick AD, English CA. Fundamental aspects of radiation induced segregation in Fe-Cr-Ni alloys. In: Proc radiation-induced sensitisation of stainless steels. Berkeley, Gloucestershire, UK: Central Electricity Generating Board, Berkeley Nuclear Labs, 1987: 15.
    • (1987) Proc Radiation-induced Sensitisation of Stainless Steels , vol.15
    • Perks, J.M.1    Marwick, A.D.2    English, C.A.3
  • 191
    • 84860159213 scopus 로고
    • London, UK: British Nuclear Energy Society, October 23 - 27
    • Proc Water Chemistry of Nuclear Reactor Systems, No.5. London, UK: British Nuclear Energy Society, October 23 - 27, 1989.
    • (1989) Proc Water Chemistry of Nuclear Reactor Systems , Issue.5
  • 192
    • 84982692071 scopus 로고    scopus 로고
    • The effect of chloride and sulfate transients on the stress corrosion cracking behavior of low alloy RPV steels under simulated BWR environment
    • NACE, Paper No. 04680
    • Ritter S, Seifert HP. The effect of chloride and sulfate transients on the stress corrosion cracking behavior of low alloy RPV steels under simulated BWR environment. In: Corrosion 2004. NACE, 2004: Paper No. 04680.
    • (2004) Corrosion 2004
    • Ritter, S.1    Seifert, H.P.2
  • 194
    • 0028483357 scopus 로고
    • A review of irradiation assisted stress-corrosion cracking
    • Scott P. A review of irradiation assisted stress-corrosion cracking. J Nucl Mater 1994; 211: 101 - 122.
    • (1994) J Nucl Mater , vol.211 , pp. 101-122
    • Scott, P.1
  • 196
    • 84865587753 scopus 로고    scopus 로고
    • Final review of the cooperative irradiation-assisted stress corrosion cracking research program
    • Scott P. Final review of the cooperative irradiation-assisted stress corrosion cracking research program. Final Report, 1020986. EPRI, 2010.
    • (2010) Final Report, 1020986, EPRI
    • Scott, P.1
  • 197
    • 1942510519 scopus 로고    scopus 로고
    • An Analysis of Baffle/Former Bolt Cracking in French PWRs
    • Scott PM, Meunier M-C, Deydier D, Silvestre S, Trenty A. An analysis of baffl e/former bolt cracking in French PWRs. In: ASTM STP 1401, Environmentally Assisted Cracking: Predictive Methods for Risk Assessment and Evaluation of Materials, Equipment and Structures. West Conshohocken, PA: ASTM International, 2000: 210 - 223. (Pubitemid 33700977)
    • (2001) ASTM Special Technical Publication , Issue.1401 , pp. 210-223
    • Scott, P.M.1    Meunier, M.-C.2    Deydier, D.3    Silvestre, S.4    Trenty, A.5
  • 198
    • 0001481491 scopus 로고
    • On the theory of radiation damage and radiation hardening
    • New York, NY: United Nations
    • Seeger A. On the theory of radiation damage and radiation hardening. In: Proc 2nd United Nations Int Conf. on Peaceful Uses of Atomic Energy, Vol. 6. New York, NY: United Nations, 1958: 250.
    • (1958) Proc 2nd United Nations Int Conf. on Peaceful Uses of Atomic Energy , vol.6 , pp. 250
    • Seeger, A.1
  • 199
    • 7644228572 scopus 로고    scopus 로고
    • Progress in the mechanistic understanding of BWR SCC and its implication to the prediction of SCC growth behavior in plants
    • Stevenson, WA: ANS
    • Shoji T. Progress in the mechanistic understanding of BWR SCC and its implication to the prediction of SCC growth behavior in plants. In: Proc 11th Int Conf on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors. Stevenson, WA: ANS, 2003: 588 - 599.
    • (2003) Proc 11th Int Conf on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors , pp. 588-599
    • Shoji, T.1
  • 200
    • 74849126180 scopus 로고    scopus 로고
    • Formulating stress corrosion cracking growth rates by combination of crack tip mechanics and crack tip oxidation kinetics
    • Shoji T, Lu Z, Murakami H. Formulating stress corrosion cracking growth rates by combination of crack tip mechanics and crack tip oxidation kinetics. Corros Sci 2010; 52: 769 - 779.
    • (2010) Corros Sci , vol.52 , pp. 769-779
    • Shoji, T.1    Lu, Z.2    Murakami, H.3
  • 201
    • 0031248584 scopus 로고    scopus 로고
    • Radiation hardening revisited: Role of intracascade clustering
    • PII S0022311597002316
    • Singh BN, Foreman AJE, Trinkaus H. Radiation hardening revisited: role of intracascade clustering. J Nucl Mater 1997; 249: 103 - 115. (Pubitemid 127375809)
    • (1997) Journal of Nuclear Materials , vol.249 , Issue.2-3 , pp. 103-115
    • Singh, B.N.1    Foreman, A.J.E.2    Trinkaus, H.3
  • 202
    • 0033489127 scopus 로고    scopus 로고
    • Stress corrosion cracking of stabilized austenitic stainless steels in various types of nuclear power plants
    • Warrendale, PA: The Metallurgical Society of The American Institute of Mining, Metallurgical, and Petroleum Engineers (AIME
    • Speidel MO, Magdowski R. Stress corrosion cracking of stabilized austenitic stainless steels in various types of nuclear power plants. In: Proc 9th Int Symp on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors. Warrendale, PA: The Metallurgical Society of The American Institute of Mining, Metallurgical, and Petroleum Engineers (AIME), 1999: 325.
    • (1999) Proc 9th Int Symp on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors , vol.325
    • Speidel, M.O.1    Magdowski, R.2
  • 205
    • 0030402460 scopus 로고    scopus 로고
    • Primary damage formation in irradiated materials
    • Stoller R. Primary damage formation in irradiated materials. J Met 1996; 48: 23.
    • (1996) J Met , pp. 23-48
    • Stoller, R.1
  • 206
    • 0014732412 scopus 로고
    • High burnup irradiation experience in vulcain
    • Storrer JT, Locke DH. High burnup irradiation experience in vulcain. Nucl Eng Inter 1970; 2: 93 - 99.
    • (1970) Nucl Eng Inter , vol.2 , pp. 93-99
    • Storrer, J.T.1    Locke, D.H.2
  • 207
    • 84996153996 scopus 로고
    • The existence of microcracks after cold-work
    • Stroh AN. The existence of microcracks after cold-work. Philos Mag 1957; 2: 1 - 4.
    • (1957) Philos Mag , vol.2 , pp. 1-4
    • Stroh, A.N.1
  • 209
    • 0000418781 scopus 로고
    • Dislocation substructure vs. transgranular stress corrosion susceptibility of single phase alloys
    • Swann PR. Dislocation substructure vs. transgranular stress corrosion susceptibility of single phase alloys. Corrosion 1963; 19: 102t.
    • (1963) Corrosion , vol.19
    • Swann, P.R.1
  • 211
    • 0026102988 scopus 로고
    • Response of electrochemical sensors to ionizing radiation in high temperature aqueous environments
    • Houston, TX: NACE, Paper No. 501
    • Taylor DF. Response of electrochemical sensors to ionizing radiation in high temperature aqueous environments. In: CORROSION/90. Houston, TX: NACE, 1990: Paper No. 501.
    • (1990) CORROSION/90
    • Taylor, D.F.1
  • 212
    • 84860185590 scopus 로고
    • High temperature aqueous crevice corrosion in alloy 600 and 304L stainless steel
    • New York, NY: The American Institute of Mining, Metallurgical, and Petroleum Engineers (AIME)
    • Taylor DF, Caramihas CA. 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, Metallurgical, and Petroleum Engineers (AIME), 1983.
    • (1983) Localized Crack Chemistry and Mechanics of Environmentally Assisted Cracking
    • Taylor, D.F.1    Caramihas, C.A.2
  • 213
    • 0033489337 scopus 로고    scopus 로고
    • Insights into environmental degradation mechanisms from analytical transmission electron microscopy of SCC cracks
    • Warrendale, PA: The Metallurgical Society of The American Institute of Mining, Metallurgical, and Petroleum Engineers (AIME
    • Thomas LE, Bruemmer SM. Insights into environmental degradation mechanisms from analytical transmission electron microscopy of SCC cracks. In: Proc 9th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors. Warrendale, PA: The Metallurgical Society of The American Institute of Mining, Metallurgical, and Petroleum Engineers (AIME), 1999: 41.
    • (1999) Proc 9th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors , vol.41
    • Thomas, L.E.1    Bruemmer, S.M.2
  • 214
    • 0003128433 scopus 로고
    • The role of metallurgical variables in hydrogen assisted environmental fracture
    • New York, NY: Plenum Press
    • Thompson AW, Bernstein IM. The role of metallurgical variables in hydrogen assisted environmental fracture. In: Advances in corrosion science and technology, Vol. 7. New York, NY: Plenum Press, 1980: 53.
    • (1980) Advances in Corrosion Science and Technology , vol.7 , pp. 53
    • Thompson, A.W.1    Bernstein, I.M.2
  • 216
  • 217
    • 84860185592 scopus 로고
    • Fracture toughness and tensile properties of irradiated austenitic stainless steel components removed from service
    • Valo M. Fracture toughness and tensile properties of irradiated austenitic stainless steel components removed from service. VTT Report DNo REA 35/91. 1993.
    • (1993) VTT Report DNo REA 35/91
    • Valo, M.1
  • 222
    • 0028444523 scopus 로고
    • Radiation-induced segregation in multicomponent alloys-effect of particle type
    • Was GS, Allen T. Radiation-induced segregation in multicomponent alloys-effect of particle type. Mater Charact 1994; 32: 239 - 255.
    • (1994) Mater Charact , vol.32 , pp. 239-255
    • Was, G.S.1    Allen, T.2
  • 223
    • 0026853350 scopus 로고
    • Irradiation-assisted stress-corrosion cracking in austenitic alloys
    • Was GS, Andresen PL. Irradiation-assisted stress-corrosion cracking in austenitic alloys. J Min Met Mat S 1992a; 44: 8 - 13.
    • (1992) J Min Met Mat S , vol.44 , pp. 8-13
    • Was, G.S.1    Andresen, P.L.2
  • 224
    • 0026853350 scopus 로고
    • Irradiation assisted stress corrosion cracking in austenitic alloys
    • Was GS, Andresen PL. Irradiation assisted stress corrosion cracking in austenitic alloys. J Met 1992b; 44: 8 - 13.
    • (1992) J Met , vol.44 , pp. 8-13
    • Was, G.S.1    Andresen, P.L.2
  • 225
    • 34248221990 scopus 로고    scopus 로고
    • Stress corrosion cracking behavior of alloys in aggressive nuclear reactor core environments
    • Was GS, Andresen PL. Stress corrosion cracking behavior of alloys in aggressive nuclear reactor core environments. Corrosion 2007; 63: 19 - 45. (Pubitemid 46722749)
    • (2007) Corrosion , vol.63 , Issue.1 , pp. 19-45
    • Was, G.S.1    Andresen, P.L.2
  • 226
    • 0032591964 scopus 로고    scopus 로고
    • Microchemistry of proton irradiated austenitic alloys under conditions relevant to LWR core components
    • Warrendale, PA: Materials Research Society
    • Was GS, Allen TR, Busby JT, Gan J, Damcott D, Carter D, Atzmon M. Microchemistry of proton irradiated austenitic alloys under conditions relevant to LWR core components. In: Proc Mater Res Soc, Vol. 540. Warrendale, PA: Materials Research Society, 1999a: 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
  • 227
    • 0032653806 scopus 로고    scopus 로고
    • Microchemistry and microstructure of protonirradiated austenitic alloys: Toward an understanding of irradiation effects in LWR core components
    • Was GS, Allen TR, Busby JT, Gan J, Damcott D, Carter D, Atzmon M, Kenik EA. Microchemistry and microstructure of protonirradiated austenitic alloys: toward an understanding of irradiation effects in LWR core components. J Nucl Mater 1999b; 270: 96 - 114.
    • (1999) J Nucl Mater , vol.270 , pp. 96-114
    • Was, G.S.1    Allen, T.R.2    Busby, J.T.3    Gan, J.4    Damcott, D.5    Carter, D.6    Atzmon, M.7    Kenik, E.A.8
  • 229
    • 0030128613 scopus 로고    scopus 로고
    • The temperature dependent role of phosphorus and titanium in microstructural evolution of Fe-Cr-Ni alloys irradiated in FFTF
    • DOI 10.1016/0022-3115(96)80004-3
    • Watanabe H, Muroga T, Yoshida N. The temperature dependent role of phosphorus and titanium in microstructural evolution of Fe-Cr-Ni alloys irradiated in FFTF. J Nucl Mater 1996; 228: 261 - 274. (Pubitemid 126392787)
    • (1996) Journal of Nuclear Materials , vol.228 , Issue.3 , pp. 261-274
    • Watanabe, H.1    Muroga, T.2    Yoshida, N.3
  • 230
    • 0018503537 scopus 로고
    • Theory of radiation-induced segregation in concentrated alloys
    • Wiedersich H, Okamoto PR, Lam NQ. A theory of radiation-induced segregation in concentrated alloys. J Nucl Mater 1979; 83: 98 - 108. (Pubitemid 9475783)
    • (1979) J Nucl Mater , vol.83 , Issue.1 , pp. 98-108
    • Wiedersich, H.1    Okamoto, P.R.2    Lam, N.Q.3
  • 231
    • 45849143262 scopus 로고    scopus 로고
    • SCC growth behavior of BWR core shroud materials
    • Yamashita H. SCC growth behavior of BWR core shroud materials. Int J Pres Ves Pip 2008; 85: 582 - 592.
    • (2008) Int J Pres Ves Pip , vol.85 , pp. 582-592
    • Yamashita, H.1
  • 232
    • 0033489292 scopus 로고    scopus 로고
    • Optimized chemical composition and heat treatment conditions of 316 CW and high chromium austenitic stainless steels for PWR baffl e bolts
    • Warrendale, PA: The Minerals, Metals, and Materials Society (TMS)
    • Yonezawa T, Iwamura T, Fujimoto K, Ajiki K. Optimized chemical composition and heat treatment conditions of 316 CW and high chromium austenitic stainless steels for PWR baffl e bolts. In: Proc 9th Int Symp On Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors. Warrendale, PA: The Minerals, Metals, and Materials Society (TMS), 1999: 1015.
    • (1999) Proc 9th Int Symp on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors , pp. 1015
    • Yonezawa, T.1    Iwamura, T.2    Fujimoto, K.3    Ajiki, K.4
  • 235
    • 85030661845 scopus 로고    scopus 로고
    • Crack tip strain rate: Estimates based on continuum theory and experimental measurement
    • NACE, Paper No. 01131
    • Young LM, Andresen PL, Angeliu TM. Crack tip strain rate: estimates based on continuum theory and experimental measurement. In: Corrosion 2001. NACE, 2001: Paper No. 01131.
    • (2001) Corrosion 2001
    • Young, L.M.1    Andresen, P.L.2    Angeliu, T.M.3
  • 236
    • 0027906638 scopus 로고
    • Dose dependence of the microstructural evolution in neutron-irradiated austenitic stainlesssteel
    • Zinkle SJ, Maziasz PJ, Stoller RE. Dose dependence of the microstructural evolution in neutron-irradiated austenitic stainlesssteel. J Nucl Mater 1993; 206: 266 - 286.
    • (1993) J Nucl Mater , vol.206 , pp. 266-286
    • Zinkle, S.J.1    Maziasz, P.J.2    Stoller, R.E.3


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.