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1
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79952953590
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-
Houston, TX: LaGrange Park, IL; Warrendale, PA: NACE International/ American Nuclear Society [ANS]/The Minerals, Metals, and Materials Society [TMS], 1983-2007.
-
Proc. 1st through 13th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (Houston, TX: LaGrange Park, IL; Warrendale, PA: NACE International/American Nuclear Society [ANS]/The Minerals, Metals, and Materials Society [TMS], 1983-2007).
-
Proc. 1st Through 13th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
-
-
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2
-
-
0002585992
-
Corrosion in nuclear systems: Environmentally assisted cracking in light water reactors
-
eds. P. Marcus, J. Ouder 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. Ouder (New York, NY: Marcel Dekker, 1994), p. 501-546.
-
(1994)
Corrosion Mechanisms
, pp. 501-546
-
-
Ford, F.P.1
Andresen, P.L.2
-
6
-
-
85042477516
-
Conceptual similarities and common predictive approaches for SCC in high-temperature water systems
-
Houston, TX: NACE
-
P.L. Andresen, "Conceptual Similarities and Common Predictive Approaches for SCC in High-Temperature Water Systems," paper no. 258, CORROSION/96 (Houston, TX: NACE, 1996).
-
(1996)
Paper No. 258, CORROSION/96
-
-
Andresen, P.L.1
-
7
-
-
0001846618
-
State of knowledge of radiation effects on environmental cracking in light water reactor core materials
-
Houston, TX: NACE, to 1-121
-
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 (Houston, TX: NACE, 1990), p. 1-83 to 1-121.
-
(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
-
8
-
-
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
-
11
-
-
0021570187
-
Mitigation of stress corrosion cracking through suppression of radiolytic oxygen
-
Houston, TX: NACE
-
B.M. Gordon, R.L. Cowan, C.W. Jewett, A.E. Pickett, "Mitigation of Stress Corrosion Cracking Through Suppression of Radiolytic Oxygen," Proc. 1st Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (Houston, TX: NACE, 1983), p. 893.
-
(1983)
Proc. 1st Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
, pp. 893
-
-
Gordon, B.M.1
Cowan, R.L.2
Jewett, C.W.3
Pickett, A.E.4
-
12
-
-
0008521064
-
Evaluation of in-reactor intergranular stress corrosion cracking via. electrochemical measurements
-
Houston, TX: NACE
-
M.E. Indig, G.M. Gordon, R.B. Davis, J.E. Webber, "Evaluation of In-Reactor Intergranular Stress Corrosion Cracking via. Electrochemical Measurements," Proc. 2nd Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (Houston, TX: NACE, 1985), p. 411.
-
(1985)
Proc. 2nd Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
, pp. 411
-
-
Indig, M.E.1
Gordon, G.M.2
Davis, R.B.3
Webber, J.E.4
-
13
-
-
0027856968
-
Optimizing BWR water chemistry
-
Warrendale, PA: The Minerals, Metals', and Materials Society [TMS]
-
R.L. Cowan, E. Kiss, "Optimizing BWR Water Chemistry," Proc. 6th. Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (Warrendale, PA: The Minerals, Metals', and Materials Society [TMS], 1993), p. 889.
-
(1993)
Proc. 6th. Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
, pp. 889
-
-
Cowan, R.L.1
Kiss, E.2
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14
-
-
0026850042
-
-
Y.J. Kim, L.W. Niedrach, M.E. Indig, P.L. Andresen, J. Met 44, 2 (1992): p. 14-18.
-
(1992)
J. Met
, vol.44
, Issue.2
, pp. 14-18
-
-
Kim, Y.J.1
Niedrach, L.W.2
Indig, M.E.3
Andresen, P.L.4
-
16
-
-
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 (Houston, TX: NACE, 1995), p. 735-746.
-
(1995)
Proc. 7th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems
, pp. 735-746
-
-
Hettiarachchi, S.1
Wozadlo, G.P.2
Diaz, T.P.3
Andresen, P.L.4
Cowan, R.L.5
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17
-
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79952918329
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-
Bournemouth Conf., held October London, U.K.: British Nuclear Energy Society [BNES]
-
P.L. Andresen, T.P. Diaz, "Effects of Zinc Additions on the Crack Growth Rate of Sensitized Stainless Steel and Alloys 600 and 182 in 288°C Water," Bournemouth Conf., held October (London, U.K.: British Nuclear Energy Society [BNES], 1993).
-
(1993)
Effects of Zinc Additions on the Crack Growth Rate of Sensitized Stainless Steel and Alloys 600 and 182 in 288°C Water
-
-
Andresen, P.L.1
Diaz, T.P.2
-
18
-
-
79952956515
-
Effects of zinc addition on crack growth rates in high-temperature water
-
Houston, TX: NACE
-
P.L. Andresen, T.P. Diaz, "Effects of Zinc Addition on Crack Growth Rates in High-Temperature Water," paper no. 184, CORROSION/93 (Houston, TX: NACE, 1993).
-
(1993)
Paper No. 184, CORROSION/93
-
-
Andresen, P.L.1
Diaz, T.P.2
-
19
-
-
69249127567
-
Effects of zinc additions on the stress corrosion crack growth rate of sensitized stainless steel, alloy 600, and alloy 182 weld metal in 288°C water
-
Houston, TX: NACE
-
P.L. Andresen, T.M. Angeliu, "Effects of Zinc Additions on the Stress Corrosion Crack Growth Rate of Sensitized Stainless Steel, Alloy 600, and Alloy 182 Weld Metal in 288°C Water," CORROSION/95, paper no. 409 (Houston, TX: NACE, 1995).
-
(1995)
CORROSION/95, Paper No. 409
-
-
Andresen, P.L.1
Angeliu, T.M.2
-
20
-
-
0043142089
-
-
held October London, U.K.: British Nuclear Energy Society [BNES]
-
W.J. Marble, R.L. Cowan, C.J. Wood, "Control of Cobalt-60 Deposition," Water Chemistry of Nuclear Reactor System 4, held October (London, U.K.: British Nuclear Energy Society [BNES], 1986).
-
(1986)
Control of Cobalt-60 Deposition, Water Chemistry of Nuclear Reactor System
, vol.4
-
-
Marble, W.J.1
Cowan, R.L.2
Wood, C.J.3
-
22
-
-
4644273731
-
Role of S, P, and N segregation on intergranular environmental cracking of stainless steels in high-temperature water
-
Littleton, CO: American Institute of Mining, Metallurgical, and Petroleum Engineers [AIME]
-
P.L. Andresen, C.L. Briant, "Role of S, P, and N Segregation on Intergranular Environmental Cracking of Stainless Steels in High-Temperature Water," Proc. 3rd Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-aterReactors (Littleton, CO: American Institute of Mining, Metallurgical, and Petroleum Engineers [AIME], 1988), p. 371-382.
-
(1988)
Proc. 3rd Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-aterReactors
, pp. 371-382
-
-
Andresen, P.L.1
Briant, C.L.2
-
24
-
-
7744237133
-
The effects of aqueous impurities on intergranular stress corrosion cracking of sensitized type 304 stainless steel
-
P.L. Andresen, "The Effects of Aqueous Impurities on Intergranular Stress Corrosion Cracking of Sensitized Type 304 Stainless Steel," Final Report NP3384, Contract Tl 15-3, EPRI, 1983.
-
(1983)
Final Report NP3384, Contract Tl 15-3, EPRI
-
-
Andresen, P.L.1
-
26
-
-
51849151414
-
Expert panel to evaluate the impact of high pH on primary water stress corrosion cracking of Ni-base alloys
-
July 7
-
P.L. Andresen, B. Beverskog, P.M. Scott, "Expert Panel to Evaluate the Impact of High pH on Primary Water Stress Corrosion Cracking of Ni-Base Alloys," EPRI Summary Report, July 7, 2003.
-
(2003)
EPRI Summary Report
-
-
Andresen, P.L.1
Beverskog, B.2
Scott, P.M.3
-
27
-
-
51849127126
-
Measurement of the Ni/NiO transition in Ni-Cr-Fe alloys and updated data and correlation to quantify the effect, of aqueous hydrogen on primary water SCC
-
Rockville, MD: NRC
-
S.A. Attanasio, D.S. Morton, "Measurement of the Ni/NiO Transition in Ni-Cr-Fe Alloys and Updated Data and Correlation to Quantify the Effect, of Aqueous Hydrogen on Primary Water SCC," Proc. 11th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems (Rockville, MD: NRC, 2003).
-
(2003)
Proc. 11th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems
-
-
Attanasio, S.A.1
Morton, D.S.2
-
28
-
-
33745188111
-
Measurement of the Ni/NiO phase transition in high-temperature hydrogenated water using the contact electrical resistance (CER) technique
-
Houston, TX: NACE
-
S.A. Attanasio, D.S. Morton, M.A. Ando, N.F. Panayotou, C.D. Thompson, "Measurement of the Ni/NiO Phase Transition in High-Temperature Hydrogenated Water Using the Contact Electrical Resistance (CER) Technique," Proc. 10th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems (Houston, TX: NACE, 2001).
-
(2001)
Proc. 10th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems
-
-
Attanasio, S.A.1
Morton, D.S.2
Ando, M.A.3
Panayotou, N.F.4
Thompson, C.D.5
-
29
-
-
33745204291
-
Primary water SCC understanding and characterization through fundamental understanding in the vicinity of the Ni/NiO phase transition
-
Houston, TX: NACE
-
D.S. Morton, S.A. Attanasio, G.A. Young, "Primary Water SCC Understanding and Characterization Through Fundamental Understanding in the Vicinity of the Ni/NiO Phase Transition," Proc. 10th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (Houston, TX: NACE, 2001).
-
(2001)
Proc. 10th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
-
-
Morton, D.S.1
Attanasio, S.A.2
Young, G.A.3
-
30
-
-
33745195866
-
SCC growth rates of alloy 182 and 82 welds
-
Rockville, MD: NRC
-
S. Attanasio, J. Mullen, J. Wuthrich, W. Wilkening, D. Morton, "SCC Growth Rates of Alloy 182 and 82 Welds," NRC Conf. on PWR Vessel Penetration Inspection, Cracking, and Repair (Rockville, MD: NRC, 2003).
-
(2003)
NRC Conf. on PWR Vessel Penetration Inspection, Cracking, and Repair
-
-
Attanasio, S.1
Mullen, J.2
Wuthrich, J.3
Wilkening, W.4
Morton, D.5
-
31
-
-
69249084140
-
Updated data and correlation to quantify the effect of aqueous hydrogen and low temperature on the SCC growth rate of nickel-base alloys in primary water
-
held June Palo Alto, CA: Electric Power Research Institute [EPRI]
-
D. Morton, S. Attanasio, E. Richey, O. Young, R. Etien, "Updated Data and Correlation to Quantify the Effect of Aqueous Hydrogen and Low Temperature on the SCC Growth Rate of Nickel-Base Alloys in Primary Water," Proc. Alloy 600 Conf., held June (Palo Alto, CA: Electric Power Research Institute [EPRI], 2007).
-
(2007)
Proc. Alloy 600 Conf.
-
-
Morton, D.1
Attanasio, S.2
Richey, E.3
Young, O.4
Etien, R.5
-
33
-
-
85040153553
-
Influence of dissolved hydrogen on nickel alloy SCC in high-temperature water
-
Houston, TX: NACE
-
D.S. Morton, S.A. Attanasio, J.S. Fish, M.K. Schurman, "Influence of Dissolved Hydrogen on Nickel Alloy SCC in High-Temperature Water," CORROSION/99, paper no. 447 (Houston, TX: NACE, 1999).
-
(1999)
CORROSION/99, Paper No. 447
-
-
Morton, D.S.1
Attanasio, S.A.2
Fish, J.S.3
Schurman, M.K.4
-
34
-
-
33745199942
-
Effects of hydrogen on electropotential monitoring of stress corrosion crack growth
-
LaGrange Park, IL: American Nuclear Society [ANS]
-
C.D. Thompson, D.M. Carey, N.L. Perazzo, "Effects of Hydrogen on Electropotential Monitoring of Stress Corrosion Crack Growth," 8th Int. Symp. on Environmental Degradation of Mate rials in Nuclear Power Systems (LaGrange Park, IL: American Nuclear Society [ANS], 1997), p. 366.
-
(1997)
8th Int. Symp. on Environmental Degradation of Mate Rials in Nuclear Power Systems
, pp. 366
-
-
Thompson, C.D.1
Carey, D.M.2
Perazzo, N.L.3
-
35
-
-
51849161658
-
Use of primary water chemistry in PWRs to mitigate PWSCC of Ni-base alloys
-
Seoul, Korea: Korean Nuclear Society
-
P.L. Andresen, J.A. Wilson, K.S. Ahluwalia, "Use of Primary Water Chemistry in PWRs to Mitigate PWSCC of Ni-Base Alloys," Proc. Int. Conf. on Water Chemistry of Nuclear Reactor Systems (Seoul, Korea: Korean Nuclear Society, 2006).
-
(2006)
Proc. Int. Conf. on Water Chemistry of Nuclear Reactor Systems
-
-
Andresen, P.L.1
Wilson, J.A.2
Ahluwalia, K.S.3
-
37
-
-
51849121100
-
Effects of PWR primary water chemistry on PWSCC of Ni alloys
-
Toronto, Canada: Canadian Nuclear Society
-
P.L. Andresen, J. Hickling, K.S. Ahluwalia, J.A. Wilson, "Effects of PWR Primary Water Chemistry on PWSCC of Ni Alloys," Proc. 13th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (Toronto, Canada: Canadian Nuclear Society, 2007).
-
(2007)
Proc. 13th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
-
-
Andresen, P.L.1
Hickling, J.2
Ahluwalia, K.S.3
Wilson, J.A.4
-
38
-
-
33745213546
-
Effects of PWR primary water chemistry and deaerated water on SCC
-
Warrendale, PA: The Minerals, Metals, and Materials Society [TMS]
-
P.L. Andresen, P.W. Emigh, M.M. Morra, J. Hickllng, "Effects of PWR Primary Water Chemistry and Deaerated Water on SCC," Proc. 12th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (Warrendale, PA: The Minerals, Metals, and Materials Society [TMS], 2005).
-
(2005)
Proc. 12th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
-
-
Andresen, P.L.1
Emigh, P.W.2
Morra, M.M.3
Hickllng, J.4
-
39
-
-
51849136670
-
Effects of dissolved H2, B/Li/pH, and Zn on PWSCC of alloy 600
-
held March Palo Alto, CA: Electric Power Research Institute
-
P.L. Andresen, J. Hickling, "Effects of Dissolved H2, B/Li/pH, and Zn on PWSCC of Alloy 600," EPRI Workshop on Alloy 600, held March (Palo Alto, CA: Electric Power Research Institute, 2005).
-
(2005)
EPRI Workshop on Alloy 600
-
-
Andresen, P.L.1
Hickling, J.2
-
41
-
-
84902156184
-
The Effect of pH on nickel alloy SCC and corrosion performance
-
Houston, TX: NACE
-
D.S. Morton, M. Hansen, "The Effect of pH on Nickel Alloy SCC and Corrosion Performance," paper no. 03675, CORROSION/2003 (Houston, TX: NACE, 2003).
-
(2003)
Paper No. 03675, CORROSION/2003
-
-
Morton, D.S.1
Hansen, M.2
-
44
-
-
52349106566
-
Microstructure and SCC crack growth of nickel-base alloy 182 weld metal in simulated PWR primary water
-
Toronto, Canada: Canadian Nuclear Society
-
S.M. Bruemmer, J.S. Vetrano, M.B. Toloczko, "Microstructure and SCC Crack Growth of Nickel-Base Alloy 182 Weld Metal in Simulated PWR Primary Water," Proc. 13th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (Toronto, Canada: Canadian Nuclear Society, 2007).
-
(2007)
Proc. 13th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
-
-
Bruemmer, S.M.1
Vetrano, J.S.2
Toloczko, M.B.3
-
45
-
-
79952927157
-
-
Personal communication with D.S. Morton, Lockheed Martin, Schenectady, New York, March 2007.
-
Personal communication with D.S. Morton, Lockheed Martin, Schenectady, New York, March 2007.
-
-
-
-
46
-
-
51849125084
-
Assessment of the interaction of variables in the intergranular stress corrosion crack growth rate behavior of alloys 600, 82, and 182
-
Toronto, Canada: Canadian Nuclear Society
-
D.J. Paraventi, W.C. Moshier, "Assessment of the Interaction of Variables in the Intergranular Stress Corrosion Crack Growth Rate Behavior of Alloys 600, 82, and 182," Proc. 13th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (Toronto, Canada: Canadian Nuclear Society, 2007).
-
(2007)
Proc. 13th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
-
-
Paraventi, D.J.1
Moshier, W.C.2
-
47
-
-
33745208219
-
SCC initiation testing of nickel'-based alloys using in-situ monitored uniaxial tensile specimens
-
Warrendale, PA: The Minerals, Metals, and Materials Society [TMS]
-
E. Richey, D.S. Morton, M.K. Schurman, "SCC Initiation Testing of Nickel'-Based Alloys Using In-Situ Monitored Uniaxial Tensile Specimens," Proc. 12th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (Warrendale, PA: The Minerals, Metals, and Materials Society [TMS], 2006).
-
(2006)
Proc. 12th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
-
-
Richey, E.1
Morton, D.S.2
Schurman, M.K.3
-
48
-
-
69249105049
-
Effects of hydrogen, pH, Lithium, and boron on primary water stress corrosion crack initiation in alloy 600 for temperatures in the range 320-330°C
-
Materials Reliability Program, (MRP-147)
-
Materials Reliability Program, "Effects of Hydrogen, pH, Lithium, and Boron on Primary Water Stress Corrosion Crack Initiation in Alloy 600 for Temperatures in the Range 320-330°C," EPRI Technical Report 1012145 (MRP-147), 2005.
-
(2005)
EPRI Technical Report 1012145
-
-
-
49
-
-
69249101741
-
Comparison of initiation and growth data for alloy 600
-
held June Palo Alto, CA: Electric Power Research Institute [EPRI]
-
A. Jenssen, K. Norring, M. Konig, "Comparison of Initiation and Growth Data for Alloy 600," Proc. Alloy 600 Conf., held June (Palo Alto, CA: Electric Power Research Institute [EPRI], 2007).
-
(2007)
Proc. Alloy 600 Conf.
-
-
Jenssen, A.1
Norring, K.2
Konig, M.3
|