-
1
-
-
84906760024
-
Overview of environmentally assisted cracking in LWR components
-
paper no. 02507, NACE, Houston, USA
-
R. S. PATHANIA, H. T. TANG AND A. R. MCILREE, "Overview of Environmentally Assisted Cracking in LWR Components", Corrosion/2002, paper no. 02507, NACE, Houston, USA (2002).
-
(2002)
Corrosion/2002
-
-
Pathania, R.S.1
Tang, H.T.2
Mcilree, A.R.3
-
2
-
-
0001829362
-
Theorectical prediction of SCC growth rate
-
TMS, USA
-
T. SHOJI, S. SUZUKI, R. G. BALLINGER, "Theorectical Prediction of SCC Growth Rate", Proc. 7th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, p.881, TMS, USA (1995).
-
(1995)
Proc. 7th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 881
-
-
Shoji, T.1
Suzuki, S.2
Ballinger, R.G.3
-
3
-
-
0030169292
-
On the modeling of stress corrosion cracking of iron and nickel base alloys in high temperature aqueous environments
-
P. L. ANDRESEN AND F. P. FORD, "On the Modeling of Stress Corrosion Cracking of Iron and Nickel Base Alloys in High Temperature Aqueous Environments", Corns. Sci., 38, 6, p. 1011 (1996).
-
(1996)
Corns. Sci.
, vol.38
, Issue.6
, pp. 1011
-
-
Andresen, P.L.1
Ford, F.P.2
-
5
-
-
0027813340
-
Some possible mechanisms of intergranular stress corrosion cracking of alloy 600 in PWR primary water
-
TMS, USA
-
P. M. SCOTT, M. LE CALVAR, "Some Possible Mechanisms of Intergranular Stress Corrosion Cracking of Alloy 600 in PWR Primary Water", Proc. 6th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, p.657, TMS, USA (1993).
-
(1993)
Proc. 6th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 657
-
-
Scott, P.M.1
Calvar, M.L.E.2
-
6
-
-
0033489339
-
An overview of internal oxidation as a possible explanation of intergranular stress corrosion cracking of alloy 600 in PWRs
-
TMS, Warrendale, USA
-
P. M. SCOTT, "An Overview of Internal Oxidation as a Possible Explanation of Intergranular Stress Corrosion Cracking of Alloy 600 in PWRs", Proc. 9th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, p.3, TMS, Warrendale, USA (1999).
-
(1999)
Proc. 9th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 3
-
-
Scott, P.M.1
-
8
-
-
0026243191
-
Effect of partial pressure of hydrogen on IGSCC of alloy 600 in PWR primary water
-
R. B. REBAK AND Z. SZKLARSKA-SMIALOWSKA, "Effect of Partial Pressure of Hydrogen on IGSCC of Alloy 600 in PWR Primary Water", Corrosion, 47, 10, p. 754 (1991).
-
(1991)
Corrosion
, vol.47
, Issue.10
, pp. 754
-
-
Rebak, R.B.1
Szklarska-Smialowska, Z.2
-
11
-
-
4544371264
-
Experimental and numerical approaches fro characterizing the crack growth rate of alloy 600 in PWR primary water and lifetime predication for welded structures
-
Gaithersburg, USA
-
T. SHOJI, Z. P. LU AND Q. J. PENG, "Experimental and Numerical Approaches fro Characterizing the Crack Growth Rate of Alloy 600 in PWR Primary Water and Lifetime Predication for Welded Structures", Vessel Penetration Inspection, Crack Growth and Repair Conference, Gaithersburg, USA (2003).
-
(2003)
Vessel Penetration Inspection, Crack Growth and Repair Conference
-
-
Shoji, T.1
Lu, Z.P.2
Peng, Q.J.3
-
12
-
-
0000242847
-
Crack tip microsampling and growth rate measurement in low alloy steel in high temperature water
-
P. L. ANDRESEN AND L. M. YOUNG, "Crack Tip Microsampling and Growth Rate Measurement in Low Alloy Steel in High Temperature Water", Corrosion, 51, 3, p. 233 (1995).
-
(1995)
Corrosion
, vol.51
, Issue.3
, pp. 233
-
-
Andresen, P.L.1
Young, L.M.2
-
13
-
-
0042699932
-
The crack tip solution chemistry in sensitized stainless steel in simulated boiling water reactor water studied using a microsampling technique
-
Q. PENG, G, LI AND T. SHOJI, "The Crack Tip Solution Chemistry in Sensitized Stainless Steel in Simulated Boiling Water Reactor Water Studied Using a Microsampling Technique", J. of Nuclear Sci. and Tech, 40, 6, p. 397 (2003).
-
(2003)
J. of Nuclear Sci. and Tech
, vol.40
, Issue.6
, pp. 397
-
-
Peng, Q.1
Li, G.2
Shoji, T.3
-
15
-
-
23644433668
-
Analysis of oxide film formed on type 304 stainless steel in 288°C water containing oxygen, hydrogen and hydrogen peroxide
-
Y. J. KIM, "Analysis of Oxide Film Formed on Type 304 Stainless Steel in 288°C Water Containing Oxygen, Hydrogen and Hydrogen Peroxide", Corrosion, 55, 1, p. 81 (1999).
-
(1999)
Corrosion
, vol.55
, Issue.1
, pp. 81
-
-
Kim, Y.J.1
-
16
-
-
0001382434
-
Characterization of the oxide film formed on type 316 stainless steel in 288°C water in cyclic normal and hydrogen water chemistries
-
Y. J. KIM, "Characterization of the Oxide Film Formed on Type 316 Stainless Steel in 288°C Water in Cyclic Normal and Hydrogen Water Chemistries", Corrosion, 51, 11, p. 849 (1995).
-
(1995)
Corrosion
, vol.51
, Issue.11
, pp. 849
-
-
Kim, Y.J.1
-
17
-
-
0025841933
-
The composition and properties of oxide films on type 304 stainless steel on exposure to lithiated water at 100-350°C
-
Z. SZKLARSKA-SMIALOWSKA, K. CHOU AND Z. XIA, "The Composition and Properties of Oxide Films on Type 304 Stainless Steel on Exposure to Lithiated Water at 100-350°C", Corros. Sci., 32, 5/6, p. 609 (1991).
-
(1991)
Corros. Sci.
, vol.32
, Issue.5-6
, pp. 609
-
-
Szklarska-Smialowska, Z.1
Chou, K.2
Xia, Z.3
-
18
-
-
0023126149
-
The mechanism and kinetics of corrosion product release from stainless steel in lithiated high temperature water
-
D. H. LISTER, R. D. DAVIDSON AND E. MCALPINE, "The Mechanism and Kinetics of Corrosion Product Release From Stainless Steel in Lithiated High Temperature Water", Corros. Sci., 27, 2, p. 113 (1987).
-
(1987)
Corros. Sci.
, vol.27
, Issue.2
, pp. 113
-
-
Lister, D.H.1
Davidson, R.D.2
Mcalpine, E.3
-
19
-
-
0031999068
-
The mechanism of oxide film formation on austenitic stainless steels in high temperature water
-
B. STELLWAG, "The Mechanism of Oxide Film Formation on Austenitic Stainless Steels in High Temperature Water", Corros. Sci., 40, 2/3, p. 337 (1998).
-
(1998)
Corros. Sci.
, vol.40
, Issue.2-3
, pp. 337
-
-
Stellwag, B.1
-
20
-
-
0024899197
-
The mechanism of high temperature aqueous corrosion of steel
-
J. ROBERTSON, "The Mechanism of High Temperature Aqueous Corrosion of Steel", Corros. Sci., 29, p. 1275 (1989).
-
(1989)
Corros. Sci.
, vol.29
, pp. 1275
-
-
Robertson, J.1
-
22
-
-
0026243191
-
Effect of partial pressure of hydrogen on IGSCC of alloy 600 in PWR primary water
-
R. B. REBAK AND Z. SZKLARSKA-SMIALOWSKA, "Effect of Partial Pressure of Hydrogen on IGSCC of Alloy 600 in PWR Primary Water", Corrosion, 47, 10, p. 754 (1991).
-
(1991)
Corrosion
, vol.47
, Issue.10
, pp. 754
-
-
Rebak, R.B.1
Szklarska-Smialowska, Z.2
-
23
-
-
0001558008
-
Quantitative prediction of environmentally assisted cracking
-
F. P. FORD, "Quantitative Prediction of Environmentally Assisted Cracking", Corrosion, 52, 5, p. 375 (1996).
-
(1996)
Corrosion
, vol.52
, Issue.5
, pp. 375
-
-
Ford, F.P.1
-
24
-
-
0026054336
-
A coupled environment model for stress corrosion cracking in sensitized type 304 stainless steel in LWR environments
-
D. D. MACDONALD AND M. URQUIDI-MACDONALD, "A Coupled Environment Model for Stress Corrosion Cracking in Sensitized Type 304 Stainless Steel in LWR Environments", Corros. Sci., 32, 1, p. 51 (1991).
-
(1991)
Corros. Sci.
, vol.32
, Issue.1
, pp. 51
-
-
Macdonald, D.D.1
Urquidi-Macdonald, M.2
-
25
-
-
0031128309
-
Modelling of crack chemistry in sensitized stainless steel in boiling water reactor environments
-
A. TURNBULL, "Modelling of Crack Chemistry in Sensitized Stainless Steel in Boiling Water Reactor Environments", Corros. Sci., 39, 4, p. 789 (1997).
-
(1997)
Corros. Sci.
, vol.39
, Issue.4
, pp. 789
-
-
Turnbull, A.1
-
26
-
-
0033489094
-
Comments on a proposed mechanism of internal oxidation for alloy 600 as applied to low potential SCC
-
TMS, Warrendale, USA
-
R. W. STAEHLE AND Z. FANG, "Comments on a Proposed Mechanism of Internal Oxidation for Alloy 600 as Applied to Low Potential SCC", Proc. 9th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, p. 69, TMS, Warrendale, USA (1999).
-
(1999)
Proc. 9th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 69
-
-
Staehle, R.W.1
Fang, Z.2
-
27
-
-
34249671041
-
In-situ measurement of contact electric resistance of oxide films on sensitized 304 stainless steel during slow strain rate test in high temperature water
-
Sendai, Japan
-
Y. TAKEDA, T. MASUDA AND T. SHOJI, "In-situ Measurement of Contact Electric Resistance of Oxide Films on Sensitized 304 Stainless Steel During Slow Strain Rate Test in High Temperature Water", Proc. of Asian Pacific Conf. on Fracture and Strength'01 & Inter. Conf. on Advanced Technology in Experimental Mechanics'01, p.114, Sendai, Japan (2001).
-
(2001)
Proc. of Asian Pacific Conf. on Fracture and Strength'01 & Inter. Conf. on Advanced Technology in Experimental Mechanics'01
, pp. 114
-
-
Takeda, Y.1
Masuda, T.2
Shoji, T.3
-
28
-
-
7744232155
-
Effect of strain on electric properties of oxide films growing on AISI 316L steel in simulated BWR conditions
-
Washington, USA
-
Y. TAKEDA, M. BOJINOV, H. HANNINEN ET AL, "Effect of Strain on Electric Properties of Oxide Films Growing on AISI 316L Steel in Simulated BWR Conditions", Proc. 11th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Washington, USA (2003).
-
(2003)
Proc. 11th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
-
-
Takeda, Y.1
Bojinov, M.2
Hanninen, H.3
-
29
-
-
0030381258
-
Irradiation-assisted stress corrosion cracking of austenitic stainless steels: Recent progress and new approaches
-
H. M. CHUNG, W. E. RUTHER, J. E. SANECKI ET AL, "Irradiation- Assisted Stress Corrosion Cracking of Austenitic Stainless Steels: Recent Progress and New Approaches", J. of Nucl. Mater., 239, p. 61 (1996).
-
(1996)
J. of Nucl. Mater.
, vol.239
, pp. 61
-
-
Chung, H.M.1
Ruther, W.E.2
Sanecki, J.E.3
-
30
-
-
0023810187
-
Environmentally assisted growth rate response of nonsensitized AISI 316 grade stainless steels in high temperature water
-
P. L. ANDRESEN, "Environmentally Assisted Growth Rate Response of Nonsensitized AISI 316 Grade Stainless Steels in High Temperature Water", Corrosion, 44, 7, p. 450 (1988).
-
(1988)
Corrosion
, vol.44
, Issue.7
, pp. 450
-
-
Andresen, P.L.1
-
31
-
-
0002074942
-
Importance of molybdenum on irradiation-assisted stress corrosion cracking in austenitic stainless steels
-
A. JENSSEN, L. G. LJUNGBERG, J. WALMSLEY AND S. FISHER, "Importance of Molybdenum on Irradiation-Assisted Stress Corrosion Cracking in Austenitic Stainless Steels", Corrosion, 54, 1, p. 48 (1998).
-
(1998)
Corrosion
, vol.54
, Issue.1
, pp. 48
-
-
Jenssen, A.1
Ljungberg, L.G.2
Walmsley, J.3
Fisher, S.4
-
32
-
-
0002643002
-
Effects of minor elements on IASCC of type 316 model stainless steels
-
American Nuclear Society, Inc, Illinois, USA
-
T. TSUKADA, Y. MIWA, H. NAKAJIMA AND T. KONDO, "Effects of Minor Elements on IASCC of Type 316 Model Stainless Steels", in Proc. 8th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, p. 69, American Nuclear Society, Inc, Illinois, USA (1997).
-
(1997)
Proc. 8th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 69
-
-
Tsukada, T.1
Miwa, Y.2
Nakajima, H.3
Kondo, T.4
-
33
-
-
3142558571
-
Effects of impurities on environmentally assisted crack growth of solution-annealed austenitic steels in primary water at 325°C
-
G. F. LI, Y. KANESHIMA AND T. SHOJI, "Effects of Impurities on Environmentally Assisted Crack Growth of Solution-Annealed Austenitic Steels in Primary Water at 325°C", Corrosion, 56, 5, p. 460 (2000).
-
(2000)
Corrosion
, vol.56
, Issue.5
, pp. 460
-
-
Li, G.F.1
Kaneshima, Y.2
Shoji, T.3
-
34
-
-
0023156925
-
The effects of various amounts of alloyed cerium and cerium oxide on the high temperature oxidation of Fe-10Cr and Fe-20Cr alloys
-
T. N. RHYS-JONES, H. J. GRABKE AND H. KUDIELKA, "The Effects of Various Amounts of Alloyed Cerium and Cerium Oxide on the High Temperature Oxidation of Fe-10Cr and Fe-20Cr Alloys", Corros. Sci., 27, 1, p. 49 (1987).
-
(1987)
Corros. Sci.
, vol.27
, Issue.1
, pp. 49
-
-
Rhys-Jones, T.N.1
Grabke, H.J.2
Kudielka, H.3
-
35
-
-
0242407115
-
Oxidation performance of a Fe-13Cr alloy with additions of rare earth elements
-
A. MARTINEZ-VILLAFANE, J. G. CHACON-NAVA AND C. GAONA-TIBURCIO ET AL, "Oxidation Performance of a Fe-13Cr Alloy With Additions of Rare Earth Elements", Materials Science and Engineering A, 363, 1-2, p.15 (2003).
-
(2003)
Materials Science and Engineering A
, vol.363
, Issue.1-2
, pp. 15
-
-
Martinez-Villafane, A.1
Chacon-Nava, J.G.2
Gaona-Tiburcio, C.3
-
36
-
-
0004378575
-
-
Sendai, Japan
-
T. TONOZUKA, Y. WATANABE, T. KONDO, T. SHOJI AND F. MASUYAMA, Proc. of the Inter. Workshop on Environmentally Assisted Cracking in Nuclear Power Plants, p. 31, Sendai, Japan (1998).
-
(1998)
Proc. of the Inter. Workshop on Environmentally Assisted Cracking in Nuclear Power Plants
, pp. 31
-
-
Tonozuka, T.1
Watanabe, Y.2
Kondo, T.3
Shoji, T.4
Masuyama, F.5
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