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2
-
-
0020910779
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H. Hänninen, K. Törrönen, M. Kemppainen, S. Salonen, Corros. Sci. 23 (1983): p. 663-679.
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(1983)
Corros. Sci.
, vol.23
, pp. 663-679
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-
Hänninen, H.1
Törrönen, K.2
Kemppainen, M.3
Salonen, S.4
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7
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0013011479
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E. Tenckhoff, M. Erve, E. Lenz, G. Vazoukis, Nucl. Eng. Des. 119 (1990): p. 371-378.
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Nucl. Eng. Des.
, vol.119
, pp. 371-378
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-
Tenckhoff, E.1
Erve, M.2
Lenz, E.3
Vazoukis, G.4
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9
-
-
0033489269
-
"European Round Robin on Constant Load EAC Tests of Low-Alloy Steel under BWR Conditions"
-
held August 1-5 (ANS/NACE International/TMS)
-
D. Blind, F. Hüttner, F. Wünsche, A. Küster, H.P. Seifert, J. Heldt, "European Round Robin on Constant Load EAC Tests of Low-Alloy Steel under BWR Conditions," Proc. 9th Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, held August 1-5 (ANS/NACE International/TMS, 1999), p. 911-919.
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(1999)
Proc. 9th Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 911-919
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-
Blind, D.1
Hüttner, F.2
Wünsche, F.3
Küster, A.4
Seifert, H.P.5
Heldt, J.6
-
10
-
-
33646224038
-
"Characterization of the Effect of Loading Frequency on Corrosion Fatigue Crack Growth Rate in RPV Steels"
-
(AMS)
-
J.D. Atkinson, J. Yu, Z.J. Zhao, "Characterization of the Effect of Loading Frequency on Corrosion Fatigue Crack Growth Rate in RPV Steels," Proc. 8th Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (AMS, 1997), p. 924-931.
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(1997)
Proc. 8th Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 924-931
-
-
Atkinson, J.D.1
Yu, J.2
Zhao, Z.J.3
-
11
-
-
0018000634
-
-
T. Shoji, S. Aiyama, H. Takahashi, M. Suzuki, Corrosion 34 (1978): p. 276-282.
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(1978)
Corrosion
, vol.34
, pp. 276-282
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-
Shoji, T.1
Aiyama, S.2
Takahashi, H.3
Suzuki, M.4
-
12
-
-
0027851144
-
"Influence of Mean Stress and Temperature on Corrosion Fatigue Crack Growth of Reactor Pressure Vessel Steels"
-
(AMS)
-
D.R. Tice, D. Worswick, P. Hurst, H. Fairbrother, "Influence of Mean Stress and Temperature on Corrosion Fatigue Crack Growth of Reactor Pressure Vessel Steels," Proc. 6th Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (AMS, 1993), p. 19-27.
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(1993)
Proc. 6th Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 19-27
-
-
Tice, D.R.1
Worswick, D.2
Hurst, P.3
Fairbrother, H.4
-
14
-
-
0010635174
-
"Effect of Hydrogen Additions to Water on the Corrosion Fatigue Behavior of Nuclear Structural Materials"
-
held September (ANS/AIME/NACE)
-
T.A. Prater, W.R. Catlin, L.F. Coffin, "Effect of Hydrogen Additions to Water on the Corrosion Fatigue Behavior of Nuclear Structural Materials," Proc. 2nd Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, held September (ANS/ AIME/NACE, 1985), p. 615-623.
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(1985)
Proc. 2nd Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 615-623
-
-
Prater, T.A.1
Catlin, W.R.2
Coffin, L.F.3
-
19
-
-
0343856633
-
"Temperature and Environmentally Assisted Cracking in Low-Alloy Steel"
-
(Houston, TX: NACE)
-
T.A. Auten, J.V. Monter, "Temperature and Environmentally Assisted Cracking in Low-Alloy Steel," Proc. 7th Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (Houston, TX: NACE, 1995), p. 1,145-1,155.
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(1995)
Proc. 7th Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
-
-
Auten, T.A.1
Monter, J.V.2
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27
-
-
85046721331
-
"Strain-Induced Corrosion Cracking of Low-Alloy Reactor Pressure Vessel Steels under BWR Conditions"
-
CORROSION/2002, paper no. 516 (Houston, TX: NACE)
-
S. Ritter, H.P. Seifert, "Strain-Induced Corrosion Cracking of Low-Alloy Reactor Pressure Vessel Steels under BWR Conditions," CORROSION/2002, paper no. 516 (Houston, TX: NACE, 2002).
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(2002)
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-
Ritter, S.1
Seifert, H.P.2
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29
-
-
0021541219
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-
J. Congleton, H.C. Shih, T. Shoji, R.N. Parkins, Corros. Sci. 25 (1985): p. 769-788.
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(1985)
Corros. Sci.
, vol.25
, pp. 769-788
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-
Congleton, J.1
Shih, H.C.2
Shoji, T.3
Parkins, R.N.4
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30
-
-
0342268344
-
-
held September (Breckenridge, Monterey, CA)
-
P. Hurst, P. Banks, G. Pemberton, A.S. Raffel, Proc. 2nd Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, held September (Breckenridge, Monterey, CA: 1985), p. 645-657.
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(1985)
Proc. 2nd Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 645-657
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-
Hurst, P.1
Banks, P.2
Pemberton, G.3
Raffel, A.S.4
-
33
-
-
0009492404
-
"Stress Corrosion Cracking of Low-Alloy Steels in High-Temperature Water"
-
held August 25-29 (AMS)
-
F.P. Ford, P.L. Andresen, D. Weinstein, S. Ranganath, R. Pathania, "Stress Corrosion Cracking of Low-Alloy Steels in High-Temperature Water," Proc. 5th Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, held August 25-29 (AMS, 1991), p. 561-570.
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(1991)
Proc. 5th Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 561-570
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-
Ford, F.P.1
Andresen, P.L.2
Weinstein, D.3
Ranganath, S.4
Pathania, R.5
-
35
-
-
33646226040
-
"Evaluation of Stress Corrosion Crack Growth in Low-Alloy Steel Vessel Materials in the BWR Environment (BWRVIP60)"
-
Final Report, EPRI TR-108709, March
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N.G. Cofie, "Evaluation of Stress Corrosion Crack Growth in Low-Alloy Steel Vessel Materials in the BWR Environment (BWRVIP60)," Final Report, EPRI TR-108709, March 1999.
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(1999)
-
-
Cofie, N.G.1
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39
-
-
85039394507
-
"Fatigue Crack Growth Rate Curves for Ferritic Steels in PWR Water Environment"
-
Cases of ASME Boiler and Pressure Vessel Code-Case N-643, ASME Committee
-
Cases of ASME Boiler and Pressure Vessel Code-Case N-643, "Fatigue Crack Growth Rate Curves for Ferritic Steels in PWR Water Environment," ASME Committee, 2001.
-
(2001)
-
-
-
41
-
-
0003483748
-
"Corrosion-Assisted Cracking of Stainless and Low-Alloy Steels in LWR Environments"
-
Final Report, EPRI NP-5064M, February
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F.P. Ford, D.F. Taylor, P.L. Andresen, "Corrosion-Assisted Cracking of Stainless and Low-Alloy Steels in LWR Environments," Final Report, EPRI NP-5064M, February 1987.
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(1987)
-
-
Ford, F.P.1
Taylor, D.F.2
Andresen, P.L.3
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42
-
-
0002139532
-
"Development and Use of a Predictive Model of Crack Propagation in 304/316L, A533b/A508, and Inconel 600/182 Alloys in 288°C Water"
-
(AMS)
-
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 Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (AMS, 1988), p. 789-800.
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(1988)
Proc. 3rd Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 789-800
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-
Ford, F.P.1
Andresen, P.L.2
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43
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-
0004297118
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-
E.D. Eason, S.P. Andrew, S.B. Warmbrodt, E.E. Nelson, J.D. Gilman, Nucl. Eng. Des. 115 (1989): p. 23-30.
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(1989)
Nucl. Eng. Des.
, vol.115
, pp. 23-30
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Eason, E.D.1
Andrew, S.P.2
Warmbrodt, S.B.3
Nelson, E.E.4
Gilman, J.D.5
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44
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-
0347623714
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-
J.D. Atkinson, J. Yu, Z.Y. Chen, Z.J. Zhao, Nucl. Eng. Des. 184 (1998): p. 13-25.
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(1998)
Nucl. Eng. Des.
, vol.184
, pp. 13-25
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-
Atkinson, J.D.1
Yu, J.2
Chen, Z.Y.3
Zhao, Z.J.4
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47
-
-
85039396872
-
"Standard Test Method for Plane-Strain Fracture Toughness of Metallic Materials"
-
ASTM E399-90, (West Conshohocken, PA: ASTM International)
-
ASTM E399-90, "Standard Test Method for Plane-Strain Fracture Toughness of Metallic Materials," in Annual Book of ASTM Standards, vol. 03.01 (West Conshohocken, PA: ASTM International, 1998).
-
(1998)
Annual Book of ASTM Standards
, vol.3
, Issue.1
-
-
-
48
-
-
85039408556
-
"Standard Test Method for Measurement of Fatigue Crack Growth Rates:
-
ASTM E647-95a, (West Conshohocken, PA: ASTM International)
-
ASTM E647-95a, "Standard Test Method for Measurement of Fatigue Crack Growth Rates,:in 1998 Annual Book of ASTM Standards, vol. 03.01 (West Conshohocken, PA: ASTM International, 1998).
-
(1998)
1998 Annual Book of ASTM Standards
, vol.3
, Issue.1
-
-
-
50
-
-
0001368770
-
"The Significance of Fatigue Crack Growth"
-
ASTM STP 486, (West Conshohocken, PA: ASTM International)
-
W. Elber, ASTM STP 486, "The Significance of Fatigue Crack Growth" (West Conshohocken, PA: ASTM International, 1971), p. 230-242.
-
(1971)
, pp. 230-242
-
-
Elber, W.1
-
51
-
-
0000534797
-
"Crack Tip Microsampling and Growth Rate Measurements in a 0.021%S Low-Alloy Steel in High-Temperature Water"
-
(Houston, TX: NACE)
-
P.L. Andresen, L.M. Young, "Crack Tip Microsampling and Growth Rate Measurements in a 0.021%S Low-Alloy Steel in High-Temperature Water," Proc. 7th Int. Symp. of Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (Houston, TX: NACE, 1995), p. 579-596.
-
(1995)
Proc. 7th Int. Symp. of Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 579-596
-
-
Andresen, P.L.1
Young, L.M.2
-
53
-
-
0003475397
-
"Computer-Calculated Potential pH Diagrams to 300°C"
-
Final Report, EPRI NP-3137, June pp. 5-3
-
C.M. Chen, K. Aral, G.J. Theus, "Computer-Calculated Potential pH Diagrams to 300°C," Final Report, EPRI NP-3137, vol. 2, June 1983, pp. 5-3, 5-14.
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(1983)
, vol.2
, pp. 5-14
-
-
Chen, C.M.1
Aral, K.2
Theus, G.J.3
-
55
-
-
0343856632
-
"On the Role of Sulfur on the Dissolution of Pressure Vessel Steels at the Tip of a Propagating Crack in PWR Environments"
-
(Houston, TX: NACE)
-
P. Cambrade, M. Foucault, P. Marcus, G. Slama, "On the Role of Sulfur on the Dissolution of Pressure Vessel Steels at the Tip of a Propagating Crack in PWR Environments," Proc. 4th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (Houston, TX: NACE, 1990), p. 8.48-8.63.
-
(1990)
Proc. 4th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
-
-
Cambrade, P.1
Foucault, M.2
Marcus, P.3
Slama, G.4
-
56
-
-
0345396694
-
-
(London, U.K.: Her Majesty's Stationery Office)
-
G. Gabetta, E. Caretta, Corrosion Chemistry Within Pits, Crevices, and Cracks (London, U.K.: Her Majesty's Stationery Office, 1987), p. 287.
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(1987)
Corrosion Chemistry Within Pits, Crevices, and Cracks
, pp. 287
-
-
Gabetta, G.1
Caretta, E.2
-
58
-
-
0025398871
-
"Environmental Acceleration of Fatigue Crack Growth in Reactor Pressure Vessel Materials and Environments"
-
ASTM STP 1049, (West Conshohocken, PA: ASTM International)
-
W.A. Van Der Sluys, R.H. Emanuelson, ASTM STP 1049, "Environmental Acceleration of Fatigue Crack Growth in Reactor Pressure Vessel Materials and Environments" (West Conshohocken, PA: ASTM International, 1990), p. 117-135.
-
(1990)
, pp. 117-135
-
-
Van Der Sluys, W.A.1
Emanuelson, R.H.2
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