-
1
-
-
0033338807
-
-
S.M. Bruemmer, E.P. Simonen, P.M. Scott, P.L. Andresen, G.S. Was, J.L. Nelson, J. Nucl. Mater. 274 (1999): p. 299.
-
(1999)
J. Nucl. Mater
, vol.274
, pp. 299
-
-
Bruemmer, S.M.1
Simonen, E.P.2
Scott, P.M.3
Andresen, P.L.4
Was, G.S.5
Nelson, J.L.6
-
2
-
-
0002585992
-
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
-
-
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
-
-
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.
-
-
-
-
7
-
-
0001846618
-
State of Knowledge of Radiation Effects on Environmental Cracking in Light Water Reactor Core Materials
-
eds. D. Cubicciotti, G.J. Theus Houston, TX: NACE International
-
P.L. Andresen, F.P. Ford, S.M. Murphy, J.M. Perks, "State of Knowledge of Radiation Effects on Environmental Cracking in Light Water Reactor Core Materials," Proc. 4th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, eds. D. Cubicciotti, G.J. Theus (Houston, TX: NACE International, 1990), p. 1-83.
-
(1990)
Proc. 4th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 1-83
-
-
Andresen, P.L.1
Ford, F.P.2
Murphy, S.M.3
Perks, J.M.4
-
9
-
-
0002898590
-
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
-
10
-
-
0013017963
-
Modeling and Prediction of Irradiation-Assisted Stress Corrosion Cracking
-
Houston, TX: NACE
-
P.L. Andresen, F.P. Ford, "Modeling and Prediction of Irradiation-Assisted Stress Corrosion Cracking," Proc. 7th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (Houston, TX: NACE, 1995), p. 893-908.
-
(1995)
Proc. 7th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 893-908
-
-
Andresen, P.L.1
Ford, F.P.2
-
11
-
-
0022192156
-
Irradiation-Assisted Stress Corrosion Cracking as a Factor in Nuclear Power Plant Aging
-
Materials Park, OH: ASM International
-
A.J. Jacobs, G.P. Wozadlo, "Irradiation-Assisted Stress Corrosion Cracking as a Factor in Nuclear Power Plant Aging," Proc. Int. Conf. on Nuclear Power Plant Aging, Availability Factor and Reliability Analysis (Materials Park, OH: ASM International, 1985), p. 173.
-
(1985)
Proc. Int. Conf. on Nuclear Power Plant Aging, Availability Factor and Reliability Analysis
, pp. 173
-
-
Jacobs, A.J.1
Wozadlo, G.P.2
-
12
-
-
0021555525
-
Behavior of Water Reactor Core Materials with Respect to Corrosion Attack
-
Houston, TX: NACE
-
F. Garzarolli, H. Rubel, E. Steinberg, "Behavior of Water Reactor Core Materials with Respect to Corrosion Attack," Proc. Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (Houston, TX: NACE, 1984), p. 1-24.
-
(1984)
Proc. Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 1-24
-
-
Garzarolli, F.1
Rubel, H.2
Steinberg, E.3
-
13
-
-
0642328305
-
Environment-Sensitive Cracking of Reactor Internals
-
H. Hanninen, I. Aho-Mantila, "Environment-Sensitive Cracking of Reactor Internals," Proc. 3rd Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (New York, NY: The American Institute of Mining, Metallurgical, and Petroleum Engineers [AIME], 1988), p. 77-92.
-
(1988)
Proc. 3rd Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (New York, NY: The American Institute of Mining, Metallurgical, and Petroleum Engineers [AIME]
, pp. 77-92
-
-
Hanninen, H.1
Aho-Mantila, I.2
-
14
-
-
34248185742
-
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
-
16
-
-
34248193060
-
-
R.N. Duncan, W.H. Arlt, H.E. Williamson, G.S. Baroch, J.P. Hoffman, T.J. Pashos, Nucl Appl. 1 (1965): p. 413.
-
(1965)
Nucl Appl
, vol.1
, pp. 413
-
-
Duncan, R.N.1
Arlt, W.H.2
Williamson, H.E.3
Baroch, G.S.4
Hoffman, J.P.5
Pashos, T.J.6
-
18
-
-
34248150621
-
-
T.J. Pashos, R.N. Duncan, H.E. Williamson, W.H. Arlt, C.J. Baroch, J.P. Hoffman, Trans. Am. Nucl. Soc. 7, 2 (1964): p. 416.
-
(1964)
Trans. Am. Nucl. Soc
, vol.7
, Issue.2
, pp. 416
-
-
Pashos, T.J.1
Duncan, R.N.2
Williamson, H.E.3
Arlt, W.H.4
Baroch, C.J.5
Hoffman, J.P.6
-
24
-
-
85040268608
-
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
-
27
-
-
0542401379
-
Dependence of Creviced BWR Component IGSCC Behavior on Coolant Chemistry
-
Houston, TX: NACE, to
-
G.M. Gordon, K.S. Brown, "Dependence of Creviced BWR Component IGSCC Behavior on Coolant Chemistry," Proc. 4th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (Houston, TX: NACE, 1990), p. 14-46 to 14-62.
-
(1990)
Proc. 4th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
-
-
Gordon, G.M.1
Brown, K.S.2
-
28
-
-
0010660153
-
Effects of BWR Coolant Chemistry on the Propensity for IGSCC Initiation and Growth in Creviced Reactor Internals Components
-
K.S. Brown, G.M. Gordon, "Effects of BWR Coolant Chemistry on the Propensity for IGSCC Initiation and Growth in Creviced Reactor Internals Components," Proc. 3rd Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (New York, NY: The American Insititute of Mining, Metallurgical, and Petroleum Engineers [AIME], 1988), p. 243-248.
-
(1988)
Proc. 3rd Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (New York, NY: The American Insititute of Mining, Metallurgical, and Petroleum Engineers [AIME]
, pp. 243-248
-
-
Brown, K.S.1
Gordon, G.M.2
-
29
-
-
0000801486
-
-
R.M. Horn, G.M. Gordon, F.P. Ford, R.L. Cowan, Nucl. Eng. Des. 174 (1997): p. 313-325.
-
(1997)
Nucl. Eng. Des
, vol.174
, pp. 313-325
-
-
Horn, R.M.1
Gordon, G.M.2
Ford, F.P.3
Cowan, R.L.4
-
30
-
-
1642338236
-
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
-
-
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.
-
-
-
-
32
-
-
0040125087
-
Compositional Profiles at Grain Boundaries in 20%Cr/25%Ni/Nb Stainless Steel
-
London, U.K, Central Electricity Generating Board
-
D.I.R. Norris, C. Baker, J.M. Titchmarsh, "Compositional Profiles at Grain Boundaries in 20%Cr/25%Ni/Nb Stainless Steel," Proc. Radiation-Induced Sensitization of Stainless Steels, Berkeley Nuclear Labs (London, U.K.: Central Electricity Generating Board, 1987), p. 86-98.
-
(1987)
Proc. Radiation-Induced Sensitization of Stainless Steels, Berkeley Nuclear Labs
, pp. 86-98
-
-
Norris, D.I.R.1
Baker, C.2
Titchmarsh, J.M.3
-
33
-
-
0012957899
-
Deformability of Austenitic Stainless Steels and Nickel-Based Alloys in the Core of a Boiling and a Pressurized Water Reactor
-
F. Garzarolli, D. Alter, P. Dewes, J.L. Nelson, "Deformability of Austenitic Stainless Steels and Nickel-Based Alloys in the Core of a Boiling and a Pressurized Water Reactor," Proc. 3rd Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (New York, NY: The American Institute of Mining, Metallurgy, and Petroleum Engineers [AIME], 1988), p. 657-664.
-
(1988)
Proc. 3rd Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (New York, NY: The American Institute of Mining, Metallurgy, and Petroleum Engineers [AIME]
, pp. 657-664
-
-
Garzarolli, F.1
Alter, D.2
Dewes, P.3
Nelson, J.L.4
-
34
-
-
0012911059
-
Deformability of Austenitic Stainless Steels and Nickel-Based Alloys in the Core of a Boiling and a Pressurized Water Reactor
-
F. Garzarolli, D. Alter, P. Dewes, "Deformability of Austenitic Stainless Steels and Nickel-Based Alloys in the Core of a Boiling and a Pressurized Water Reactor," Proc. 2nd Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (LaGrange Park, IL: American Nuclear Society [ANS], 1986), p. 131-138.
-
(1986)
Proc. 2nd Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (LaGrange Park, IL: American Nuclear Society [ANS]
, pp. 131-138
-
-
Garzarolli, F.1
Alter, D.2
Dewes, P.3
-
36
-
-
0002604850
-
The Concept of Noble Metal Addition Technology for IGSCC Mitigation of Nuclear Materials
-
Houston, TX: NACE
-
S. Hettiarachchi, G.P. Wozadlo, T.P. Diaz, P.L. Andresen, R.L Cowan, "The Concept of Noble Metal Addition Technology for IGSCC Mitigation of Nuclear Materials," Proc. 7th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (Houston, TX: NACE, 1995), p. 735-746.
-
(1995)
Proc. 7th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 735-746
-
-
Hettiarachchi, S.1
Wozadlo, G.P.2
Diaz, T.P.3
Andresen, P.L.4
Cowan, R.L.5
-
37
-
-
34248143633
-
-
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).
-
-
-
-
40
-
-
34248217759
-
Neutron Fluence Dependent Intergranular Cracking of Thermally Sensitized Type 304 Stainless Steel at 290°C in Inert Gas and in Water
-
T. Onchi, K. Dohi, N. Soneda, M. Navas, M. Luisa Castano, "Neutron Fluence Dependent Intergranular Cracking of Thermally Sensitized Type 304 Stainless Steel at 290°C in Inert Gas and in Water," Proc. 11th Int. Conf. Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (La Grange Park, IL: American Nuclear Society [ANS], 2003). p. 1, 111.
-
(2003)
Proc. 11th Int. Conf. Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (La Grange Park, IL: American Nuclear Society [ANS]
-
-
Onchi, T.1
Dohi, K.2
Soneda, N.3
Navas, M.4
Luisa Castano, M.5
-
41
-
-
34248213302
-
-
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).
-
-
-
-
42
-
-
1942435611
-
Application of Water Chemistry Control, On-Line Monitoring, and Crack Growth Models for Improved BWR Materials Performance
-
Houston, TX: NACE, to
-
F.P. Ford, P.L. Andresen, H.D. Solomon, G.M. Gordon, S. Ranganath, D. Weinstein, R. Pathania, "Application of Water Chemistry Control, On-Line Monitoring, and Crack Growth Models for Improved BWR Materials Performance," Proc. 4th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems (Houston, TX: NACE, 1990), p. 4-26 to 4-51.
-
(1990)
Proc. 4th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems
-
-
Ford, F.P.1
Andresen, P.L.2
Solomon, H.D.3
Gordon, G.M.4
Ranganath, S.5
Weinstein, D.6
Pathania, R.7
-
43
-
-
34248196756
-
Environmentally Controlled Cracking of Stainless and Low Alloy Steels in LWR Environments
-
F.P. Ford, D.F. Taylor, P.L. Andresen, R.G. Ballinger, "Environmentally Controlled Cracking of Stainless and Low Alloy Steels in LWR Environments," Electric Power Research Institute [EPRI], NP-5064M (RP2006-6), 1987.
-
(1987)
Electric Power Research Institute [EPRI], NP-5064M (RP2006-6)
-
-
Ford, F.P.1
Taylor, D.F.2
Andresen, P.L.3
Ballinger, R.G.4
-
44
-
-
0033489379
-
Intergranular Stress Corrosion Cracking of Unsensitized Stainless Steels in BWR Environments
-
T.M. Angeliu, P.L. Andresen, J.A. Sutliff, R.M. Horn, "Intergranular Stress Corrosion Cracking of Unsensitized Stainless Steels in BWR Environments," Proc. 9th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems (The American Institute of Mining, Metallurgy, and Petroleum Engineers [AIME], 1999).
-
(1999)
Proc. 9th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems (The American Institute of Mining, Metallurgy, and Petroleum Engineers [AIME]
-
-
Angeliu, T.M.1
Andresen, P.L.2
Sutliff, J.A.3
Horn, R.M.4
-
45
-
-
85031249507
-
-
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).
-
-
-
-
46
-
-
7744227065
-
Immunity, Thresholds, and Other SCC Fiction
-
P.L. Andresen, T.M. Angeliu, L.M. Young, "Immunity, Thresholds, and Other SCC Fiction," Proc. Staehle Symp. on Chemistry and Electrochemistry of Corrosion and SCC, held February (Warrendale, PA: The Minerals, Metals, and Materials Society [TMS], 2001).
-
(2001)
Proc. Staehle Symp. on Chemistry and Electrochemistry of Corrosion and SCC, held February (Warrendale, PA: The Minerals, Metals, and Materials Society [TMS]
-
-
Andresen, P.L.1
Angeliu, T.M.2
Young, L.M.3
-
48
-
-
0000534797
-
Characterization of the Roles of Electrochemistry, Convection and Crack Chemistry in Stress Corrosion Cracking
-
Houston, TX: NACE
-
P. L. Andresen, L.M. Young, "Characterization of the Roles of Electrochemistry, Convection and Crack Chemistry in Stress Corrosion Cracking," Proc. 7th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (Houston, TX: NACE, 1995), p. 579-596.
-
(1995)
Proc. 7th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 579-596
-
-
Andresen, P.L.1
Young, L.M.2
-
52
-
-
34248159694
-
-
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
-
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
-
54
-
-
0030410116
-
Life Prediction of Boiling Water Reactor Internals
-
New York, NY: ASME International
-
P.L. Andresen, F.P. Ford, J.P. Higgins, I. Suzuki, M. Koyama, M. Akiyama, T. Okubo, Y. Mishima, S. Hattori, H. Anzai, H. Chujo, Y. Kanazawa, "Life Prediction of Boiling Water Reactor Internals," Proc. ICONE-4 Conf. (New York, NY: ASME International, 1996).
-
(1996)
Proc. ICONE-4 Conf
-
-
Andresen, P.L.1
Ford, F.P.2
Higgins, J.P.3
Suzuki, I.4
Koyama, M.5
Akiyama, M.6
Okubo, T.7
Mishima, Y.8
Hattori, S.9
Anzai, H.10
Chujo, H.11
Kanazawa, Y.12
-
55
-
-
34248137671
-
-
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
-
-
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
-
-
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
-
-
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
-
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
-
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
-
-
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
-
-
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
-
-
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.
-
-
-
-
69
-
-
0002074942
-
-
A. Jenssen, L.G. Ljungberg, J. Walmsley, S. Fisher, Corrosion 54, 1 (1998): p. 48.
-
(1998)
Corrosion
, vol.54
, Issue.1
, pp. 48
-
-
Jenssen, A.1
Ljungberg, L.G.2
Walmsley, J.3
Fisher, S.4
-
70
-
-
0032072553
-
-
T. Allen, J.T. Busby, G.S. Was, E.A. Kenik, J. Nucl. Mater. 255 (1998): p. 44.
-
(1998)
J. Nucl. Mater
, vol.255
, pp. 44
-
-
Allen, T.1
Busby, J.T.2
Was, G.S.3
Kenik, E.A.4
-
71
-
-
0032591964
-
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
-
-
Pacific Northwest National Laboratory, private communication
-
E. Simonen, Pacific Northwest National Laboratory, private communication, 2001.
-
(2001)
-
-
Simonen, E.1
-
75
-
-
34248225081
-
-
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
-
-
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
-
-
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.
-
-
-
-
79
-
-
0008268170
-
-
S. Nakahigashi, M. Kodama, K. Fukuya, S. Nishimura, S. Yamamoto, K. Saito, T. Saito, J. Nucl. Mater. 179-181 (1992): p. 1,061.
-
(1992)
J. Nucl. Mater
, vol.179-181
, pp. 1-061
-
-
Nakahigashi, S.1
Kodama, M.2
Fukuya, K.3
Nishimura, S.4
Yamamoto, S.5
Saito, K.6
Saito, T.7
-
80
-
-
0006311532
-
Influence of Grain Boundary Composition on the IASCC Susceptibility of Type 348 Stainless Steel
-
ed. D. Cubicciotti Houston, TX: NACE
-
A.J. Jacobs, R.E. Clausing, M.K. Miller, C.M. Shepherd, "Influence of Grain Boundary Composition on the IASCC Susceptibility of Type 348 Stainless Steel," Proc. 4th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, ed. D. Cubicciotti (Houston, TX: NACE, 1990), p. 14-21.
-
(1990)
Proc. 4th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 14-21
-
-
Jacobs, A.J.1
Clausing, R.E.2
Miller, M.K.3
Shepherd, C.M.4
-
81
-
-
0001921919
-
Microchemical Characterization of Grain Boundaries in Irradiated Steels
-
Houston, TX: NACE
-
J. Walmsley, P. Spellward, S. Fisher, A. Jenssen, "Microchemical Characterization of Grain Boundaries in Irradiated Steels," Proc. 7th Int. Symp. on Environment Degradation of Materials in Nuclear Power System - Water Reactors (Houston, TX: NACE, 1997), p. 985.
-
(1997)
Proc. 7th Int. Symp. on Environment Degradation of Materials in Nuclear Power System - Water Reactors
, pp. 985
-
-
Walmsley, J.1
Spellward, P.2
Fisher, S.3
Jenssen, A.4
-
82
-
-
0036468307
-
-
G.S. Was, J.T. Busby, J. Gan, E.A. Kenik. A. Jenssen, S.M. Bruemmer, P.M. Scott, P.L. Andresen, J. Nucl. Mater. 300 (2002): p. 198.
-
(2002)
J. Nucl. Mater
, vol.300
, pp. 198
-
-
Was, G.S.1
Busby, J.T.2
Gan, J.3
Kenik, E.A.4
Jenssen, A.5
Bruemmer, S.M.6
Scott, P.M.7
Andresen, P.L.8
-
83
-
-
0028465653
-
-
R. Carter, D. Damcott, M. Atzmon, G.S. Was, S.M. Bruemmer, E.A. Kenik, J. Nucl. Mater. 211 (1994): p. 70.
-
(1994)
J. Nucl. Mater
, vol.211
, pp. 70
-
-
Carter, R.1
Damcott, D.2
Atzmon, M.3
Was, G.S.4
Bruemmer, S.M.5
Kenik, E.A.6
-
84
-
-
0032591962
-
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
-
85
-
-
0033338807
-
-
S.M. Bruemmer, E.P. Simonen, P.M. Scott, P.L. Andresen, G.S. Was, J.L. Nelson, J. Nucl. Mater. 274 (1999): p. 299.
-
(1999)
J. Nucl. Mater
, vol.274
, pp. 299
-
-
Bruemmer, S.M.1
Simonen, E.P.2
Scott, P.M.3
Andresen, P.L.4
Was, G.S.5
Nelson, J.L.6
-
88
-
-
0041380836
-
-
L. Fournier, B.H. Sencer, G.S. Was, E.P. Simonen, S.M. Bruemmer, J. Nucl. Mater. 321, 2-3 (2003): p. 192-209.
-
(2003)
J. Nucl. Mater
, vol.321
, Issue.2-3
, pp. 192-209
-
-
Fournier, L.1
Sencer, B.H.2
Was, G.S.3
Simonen, E.P.4
Bruemmer, S.M.5
-
89
-
-
0942266719
-
-
J. Gan, E.P. Simonen, S.M. Bruemmer, L. Fournier, B.H. Sencer, G.S. Was, J. Nucl. Mater. 325 (2004): p. 94-106.
-
(2004)
J. Nucl. Mater
, vol.325
, pp. 94-106
-
-
Gan, J.1
Simonen, E.P.2
Bruemmer, S.M.3
Fournier, L.4
Sencer, B.H.5
Was, G.S.6
-
90
-
-
0027887734
-
-
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
-
-
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.
-
-
-
-
92
-
-
0032653806
-
-
G.S. Was, T.R. Allen, J.T. Busby, J. Gan, D. Damcott, D. Carter, M. Atzmon, E.A. Kenik, J. Nucl. Mater. 270 (1999): p. 96.
-
(1999)
J. Nucl. Mater
, vol.270
, pp. 96
-
-
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
-
95
-
-
0002559236
-
High-Temperature Solution Annealing as an IASCC Mitigation Technique
-
IL: American Nuclear Society
-
A.J. Jacobs, G.E.C. Bell, C.M. Shepherd, G.P. Wozadlo, "High-Temperature Solution Annealing as an IASCC Mitigation Technique," Proc. 5th Int. Symp. on Environment Degradation of Materials in Nuclear Power System - Water Reactor (La Grange Park, IL: American Nuclear Society, 1992), p. 917.
-
(1992)
Proc. 5th Int. Symp. on Environment Degradation of Materials in Nuclear Power System - Water Reactor (La Grange Park
, pp. 917
-
-
Jacobs, A.J.1
Bell, G.E.C.2
Shepherd, C.M.3
Wozadlo, G.P.4
-
96
-
-
0030382173
-
-
Y. Ishiyama, M. Kodama, N. Yokota, K. Asano, T. Kato, K. Fukuya, J. Nucl. Mater. 239 (1996): p. 90.
-
(1996)
J. Nucl. Mater
, vol.239
, pp. 90
-
-
Ishiyama, Y.1
Kodama, M.2
Yokota, N.3
Asano, K.4
Kato, T.5
Fukuya, K.6
-
97
-
-
85042427243
-
Post-Irradiation Annealing Effects of Austenitic Stainless Steel in IASCC
-
paper no. 132 Houston, TX: NACE
-
S. Katsura, Y. Ishiyama, N. Yokota, T. Kato, K. Nakata, K. Fukuya, H. Sakamoto, K. Asano, "Post-Irradiation Annealing Effects of Austenitic Stainless Steel in IASCC," CORROSION/98, paper no. 132 (Houston, TX: NACE, 1998).
-
(1998)
CORROSION/98
-
-
Katsura, S.1
Ishiyama, Y.2
Yokota, N.3
Kato, T.4
Nakata, K.5
Fukuya, K.6
Sakamoto, H.7
Asano, K.8
-
98
-
-
32944463309
-
-
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.
-
-
-
-
99
-
-
33745251770
-
Bulk Composition and Grain Boundary Engineering to Improve Stress Corrosion Cracking Behavior of Proton Irradiated Stainless Steels
-
IL: American Nuclear Society
-
R.B. Dropek, G.S. Was, J. Gan, J.I. Cole, T.R. Allen, E.A. Kenik, "Bulk Composition and Grain Boundary Engineering to Improve Stress Corrosion Cracking Behavior of Proton Irradiated Stainless Steels," Proc. 11th Int. Conf. Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (La Grange Park, IL: American Nuclear Society, 2003), p. 1,132.
-
(2003)
Proc. 11th Int. Conf. Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (La Grange Park
, pp. 1-132
-
-
Dropek, R.B.1
Was, G.S.2
Gan, J.3
Cole, J.I.4
Allen, T.R.5
Kenik, E.A.6
-
102
-
-
34248225080
-
-
T. Yonezawa, K. Fujimoto, H. Kanasaki, T. Iwamura, S. Nakada, K. Ajiki, S. Urata, Corros. Eng. 49 (2000): p. 655.
-
(2000)
Corros. Eng
, vol.49
, pp. 655
-
-
Yonezawa, T.1
Fujimoto, K.2
Kanasaki, H.3
Iwamura, T.4
Nakada, S.5
Ajiki, K.6
Urata, S.7
-
103
-
-
34248160710
-
-
K. Fujimoto, T. Yonezawa, T. Iwamura, K. Ajiki, S. Urata, Corros. Eng. 49 (2000): p. 701.
-
(2000)
Corros. Eng
, vol.49
, pp. 701
-
-
Fujimoto, K.1
Yonezawa, T.2
Iwamura, T.3
Ajiki, K.4
Urata, S.5
-
104
-
-
34248156930
-
-
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
-
-
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.
-
-
-
-
106
-
-
34248139863
-
-
G.F. Li, Y. Kaneshima, T. Shoji, Corrosion 56, 5 (2000): p. 540.
-
(2000)
Corrosion
, vol.56
, Issue.5
, pp. 540
-
-
Li, G.F.1
Kaneshima, Y.2
Shoji, T.3
-
112
-
-
34248150622
-
Microstructural Evaluation of a Cold-Worked 316SS Baffle Bolt Irradiated in a Commercial PWR
-
Houston, TX: NACE International
-
D.J. Edwards, B.A. Oliver, F.A. Garner, S.M. Bruemmer, "Microstructural Evaluation of a Cold-Worked 316SS Baffle Bolt Irradiated in a Commercial PWR," Proc. 10th Int. Conf. Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (Houston, TX: NACE International, 2002).
-
(2002)
Proc. 10th Int. Conf. Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
-
-
Edwards, D.J.1
Oliver, B.A.2
Garner, F.A.3
Bruemmer, S.M.4
-
113
-
-
0242585793
-
-
D.J. Edwards, E.P. Simonen, F.A. Garner, L.R. Greenwood, B.M. Oliver, S.M. Bruemmer, J. Nucl. Mater. 317 (2000): p. 32.
-
(2000)
J. Nucl. Mater
, vol.317
, pp. 32
-
-
Edwards, D.J.1
Simonen, E.P.2
Garner, F.A.3
Greenwood, L.R.4
Oliver, B.M.5
Bruemmer, S.M.6
-
114
-
-
0030402460
-
-
R. Stoller, JOM 12 (1996): p. 23.
-
(1996)
JOM
, vol.12
, pp. 23
-
-
Stoller, R.1
-
115
-
-
32144443180
-
-
J.T. Busby, M.M. Sowa, G.S. Was, E.P. Simonen, Phil. Mag. 85, 4-7 (2005): p. 609-617.
-
(2005)
Phil. Mag
, vol.85
, Issue.4-7
, pp. 609-617
-
-
Busby, J.T.1
Sowa, M.M.2
Was, G.S.3
Simonen, E.P.4
-
116
-
-
34248198092
-
Phil. Mag. A, Phys. Condens. Matter Defects Mech. Prop
-
in press
-
E.P. Simonen, D.J. Edwards, B.W. Arey, S.M. Bruemmer, J.T. Busby, G.S. Was, Phil. Mag. A, Phys. Condens. Matter Defects Mech. Prop., in press.
-
-
-
Simonen, E.P.1
Edwards, D.J.2
Arey, B.W.3
Bruemmer, S.M.4
Busby, J.T.5
Was, G.S.6
-
117
-
-
84860210389
-
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
-
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
-
-
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
-
-
A. Jenssen, ABB Atom, written communication, 1998.
-
A. Jenssen, ABB Atom, written communication, 1998.
-
-
-
-
125
-
-
0001481491
-
On the Theory of Radiation Damage and Radiation Hardening
-
New York, NY: United Nations
-
A. Seeger, "On the Theory of Radiation Damage and Radiation Hardening," Proc. 2nd United Nations Int. Conf. on Peaceful Uses of Atomic Energy, vol. 6 (New York, NY: United Nations, 1958), p. 250.
-
(1958)
Proc. 2nd United Nations Int. Conf. on Peaceful Uses of Atomic Energy
, vol.6
, pp. 250
-
-
Seeger, A.1
-
126
-
-
0027850881
-
-
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
-
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
-
-
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.
-
-
-
-
129
-
-
0029389377
-
-
A. Jacobs, G.P. Wozaldo, G.M. Gordon, Corrosion 51, 10 (1995): p. 731.
-
(1995)
Corrosion
, vol.51
, Issue.10
, pp. 731
-
-
Jacobs, A.1
Wozaldo, G.P.2
Gordon, G.M.3
-
130
-
-
32944471246
-
-
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
-
-
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
-
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
-
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
-
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
-
138
-
-
0038489354
-
-
Oak Ridge National Laboratory, report ORNL/TM, July
-
K. Farrell, T.S. Byun, N. Hashimoto, "Mapping Flow Localization Processes in Deformation of Irradiated Reactor Structural Alloys," Oak Ridge National Laboratory, report ORNL/TM-2002/66, July 2002.
-
Mapping Flow Localization Processes in Deformation of Irradiated Reactor Structural Alloys
, pp. 2002
-
-
Farrell, K.1
Byun, T.S.2
Hashimoto, N.3
-
141
-
-
0034540538
-
-
C. Bailat, A. Almazouzi, M. Baluc, R. Schaublin, F. Groschel, M. Victoria, J. Nucl. Mater. 283-287 (2000): p. 446.
-
(2000)
J. Nucl. Mater
, vol.283-287
, pp. 446
-
-
Bailat, C.1
Almazouzi, A.2
Baluc, M.3
Schaublin, R.4
Groschel, F.5
Victoria, M.6
-
142
-
-
33144459425
-
-
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
-
-
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
-
-
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
-
-
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.
-
-
-
-
147
-
-
34248196753
-
Stress Relaxation Caused by Neutron-Irradiation at 561 K in Austenitic Stainless Steels
-
IL: American Nuclear Society
-
Y. Ishiyama, K. Nakata, M. Obata, H. Anzai, S. Tanaka, T. Tsukada, K. Asano, "Stress Relaxation Caused by Neutron-Irradiation at 561 K in Austenitic Stainless Steels," Proc. 11th Intl. Conf. Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (La Grange Park, IL: American Nuclear Society, 2003), p. 920.
-
(2003)
Proc. 11th Intl. Conf. Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (La Grange Park
, pp. 920
-
-
Ishiyama, Y.1
Nakata, K.2
Obata, M.3
Anzai, H.4
Tanaka, S.5
Tsukada, T.6
Asano, K.7
-
148
-
-
0242569627
-
-
B.H. Sencer, G.S. Was, Y. Isobe, M. Sagisaka, F.A. Garner, J. Nucl. Mater. 323 (2003): p. 18-28.
-
(2003)
J. Nucl. Mater
, vol.323
, pp. 18-28
-
-
Sencer, B.H.1
Was, G.S.2
Isobe, Y.3
Sagisaka, M.4
Garner, F.A.5
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