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1
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0019231355
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Comparative stress corrosion behavior of welded austenitic stainless steel pipe in high temperature high purity oxygenated water
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J.N. Kass, J.C. Lemaire, R.B. Davis, J.E. Alexander and J.C. Danko, "Comparative Stress Corrosion Behavior of Welded Austenitic Stainless Steel Pipe in High Temperature High Purity Oxygenated Water", Corrosion, vol. 36, no. 12 (1980) 686-698.
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(1980)
Corrosion
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, pp. 686-698
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Kass, J.N.1
Lemaire, J.C.2
Davis, R.B.3
Alexander, J.E.4
Danko, J.C.5
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2
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0019028555
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Stress corrosion cracking of welded type 304 and 304l stainless steel under cyclic loading
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J.N. Kass, W.L. Walker and A.J. Giannuzzi, "Stress Corrosion Cracking of Welded Type 304 and 304L Stainless Steel Under Cyclic Loading", Corrosion, vol. 36, no. 6 (1980) 299-305.
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Corrosion
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Kass, J.N.1
Walker, W.L.2
Giannuzzi, A.J.3
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3
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33748325454
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Intergranular cracking of an aisi316ng stainless steel material in bwr environment
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submitted to the
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U. Ehrnsten, P. Aaltonen, P. Nenonen, H. Hanninen, C. Jansson and T. Angeliu, "Intergranular Cracking of an AISI316NG Stainless Steel Material in BWR Environment", submitted to the 10th Intemational Symposium on the Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors.
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10th Intemational Symposium on the Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
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Ehrnsten, U.1
Aaltonen, P.2
Nenonen, P.3
Hanninen, H.4
Jansson, C.5
Angeliu, T.6
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4
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0030473209
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Multivariate statistical analysis of feg-stem edx spectra
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J.M. Titmarch and S. Dumbill, "Multivariate Statistical Analysis of FEG-STEM EDX Spectra", Journal of Microscopy, vol. 184, pt. 3 (1996) 195-207.
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Journal of Microscopy
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Titmarch, J.M.1
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5
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33644916972
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An investigation of plastic strain in copper by automated-ebsp
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Proceedings: Microscopy & Microanalysis '99
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J.A. Sutliff, An Investigation of Plastic Strain in Copper by Automated-EBSP, Microscopy and Microanalysis, Vol 5. Supp. 2 1999 p. 236, (Proceedings: Microscopy & Microanalysis '99)
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Microscopy and Microanalysis
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Sutliff, J.A.1
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6
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0033489379
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Intergranular stress corrosion cracking of unsensitized stainless steels in bwr environments
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submitted to the
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T.M. Angeliu, P.L. Andresen, E. Hall, J.A. Sutliff, S. Sitzman and R.M. Horn, "Intergranular Stress Corrosion Cracking of Unsensitized Stainless Steels in BWR Environments", submitted to the 9th International Symposium on the Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, TMS.
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9th International Symposium on the Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, TMS
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Angeliu, T.M.1
Andresen, P.L.2
Hall, E.3
Sutliff, J.A.4
Sitzman, S.5
Horn, R.M.6
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7
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85031249507
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Strain and microstructural characterization of austenitic stainless steel weld hazs
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paper 186, NACE, Houston, TX
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T.M. Angeliu, P.L. Andresen, E. Hall, J.A. Sutliff and S. Sitzman, "Strain and Microstructural Characterization of Austenitic Stainless Steel Weld HAZs", Corrosion/00, paper 186, NACE, Houston, TX (2000).
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(2000)
Corrosion/00
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Angeliu, T.M.1
Andresen, P.L.2
Hall, E.3
Sutliff, J.A.4
Sitzman, S.5
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9
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0001358525
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Thermally induced grain boundary composition and effects on radiation-induced segregation
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American Nuclear Society, La Grange Park, IL
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E.P. Simonen and S.M. Bruemmer, "Thermally Induced Grain Boundary Composition and Effects on Radiation-Induced Segregation", 8th International Symposium on the Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, vol. 2, American Nuclear Society, La Grange Park, IL (1997) 751-757.
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(1997)
8th International Symposium on the Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
, vol.2
, pp. 751-757
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Simonen, E.P.1
Bruemmer, S.M.2
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10
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0023827821
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Non-Equilibrium Grain Boundary Segregation of Boron in Austenitic Stainless Steel -IV. Precipitation Behaviour and Distribution of Elements at Grain Boundaries
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L. Karlsson and H. Norden, "Non-Equilibrium Grain Boundary Segregation of Boron in Austenitic Stainless Steel -IV. Precipitation Behaviour and Distribution of Elements at Grain Boundaries", Acta Met. Vol. 36, no. 1 (1988) 35-48.
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(1988)
Acta Met
, vol.36
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, pp. 35-48
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Karlsson, L.1
Norden, H.2
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12
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33748301764
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The igscc behavior of l-grade stainless steels in 288°c water
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American Nuclear Society, La Grange Park, IL
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T.M. Angeliu, P.L. Andresen, M.L. Pollick, R. Horn, V. McCarthy and J. Walmsley, "The IGSCC Behavior of L-Grade Stainless Steels in 288°C Water", 8th International Symposium on the Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, vol. 2, American Nuclear Society, La Grange Park, IL (1997) 649-662.
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(1997)
8th International Symposium on the Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
, vol.2
, pp. 649-662
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Angeliu, T.M.1
Andresen, P.L.2
Pollick, M.L.3
Horn, R.4
McCarthy, V.5
Walmsley, J.6
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13
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0001921919
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Microchemical characterisation of grain boundaries in irradiated steels
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NACE, Houston, TX
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J. Walmsley, P. Spellward, S. Fisher, A. Jenssen, "Microchemical Characterisation of Grain Boundaries in Irradiated Steels", Seventh International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, NACE, Houston, TX (1995) 985-995.
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(1995)
Seventh International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
, pp. 985-995
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Walmsley, J.1
Spellward, P.2
Fisher, S.3
Jenssen, A.4
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14
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0013006178
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Stress corrosion cracking of austenitic stainless steel core internal welds
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paper, NACE, Houston, TX
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H.M. Chung, J.-H. Park, W.E. Ruther, J.E. Sanecki, R.V. Strain and N.J. Zaluzec, "Stress Corrosion Cracking of Austenitic Stainless Steel Core Internal Welds", CORROSION/99, paper, NACE, Houston, TX (1999).
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(1999)
CORROSION/99
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Chung, H.M.1
Park, J.-H.2
Ruther, W.E.3
Sanecki, J.E.4
Strain, R.V.5
Zaluzec, N.J.6
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15
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0019040918
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The influence of prior deformation on continuous cooling sensitization of type 304 stainless steel
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H.D. Solomon, "The Influence of Prior Deformation on Continuous Cooling Sensitization of Type 304 Stainless Steel", Corrosion, vol. 36, no. 7 (1980) 356-361.
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Corrosion
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, pp. 356-361
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Solomon, H.D.1
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16
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0022130783
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Influence of prior deformation and composition on continuous cooling sensitization of aisi 304 stainless steel
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H.D. Solomon, "Influence of Prior Deformation and Composition on Continuous Cooling Sensitization of AISI 304 Stainless Steel", Corrosion, vol. 41, no. 9 (1985) 512-517.
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Corrosion
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, pp. 512-517
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Solomon, H.D.1
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18
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0012961080
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Finite element stress analysis of 4-inch diameter welded pipe with prescribed residual stresses
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Electric Power Research Institute, Palo Alto, CA, paper 35
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G. Derbalian, G.R. Egan and C. Aboim-Costa, "Finite Element Stress Analysis of 4-inch Diameter Welded Pipe with Prescribed Residual Stresses", Proceedings: Seminar on Countermeasures for Pipe Cracking in BWRs, Volume 2 of 4, WS-79-174, vol. 2, Electric Power Research Institute, Palo Alto, CA, (1980) paper 35.
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(1980)
Proceedings: Seminar on Countermeasures for Pipe Cracking in BWRs, Volume 2 of 4", WS- 79-174
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Derbalian, G.1
Egan, G.R.2
Aboim-Costa, C.3
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19
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46149148809
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Stress improvement for welds in 316 nuclear grade stainless steel bwr recirculation piping part i
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Electric Power Research Institute, Palo Alto, CA, 17-1 to 17-25
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G. Krause, "Stress Improvement for Welds in 316 Nuclear Grade Stainless Steel BWR Recirculation Piping Part I", Proceedings: Second Seminar on Countermeasures for Pipe Cracking in BWRs, Volume 3: Remedy Application, NP-3684-SR, vol. 3, Electric Power Research Institute, Palo Alto, CA, (1984) 17-1 to 17-25.
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Proceedings: Second Seminar on Countermeasures for Pipe Cracking in BWRs, Volume 3: Remedy Application, NP-3684-SR
, vol.3
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Krause, G.1
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20
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29144443956
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Effect of deformation on scc of unsensitized ss
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paper 203, NACE
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P.L. Andresen and T.M. Angeliu, "Effect of Deformation on SCC of Unsensitized SS", Corrosion/00, paper 203, NACE.
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Corrosion/00
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Andresen, P.L.1
Angeliu, T.M.2
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22
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85030661845
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Crack tip strain rate: Estimates based on continuum theory and experimental measurement
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paper 131, NACE, Houston, TX
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L.M. Young, P.L. Andresen and T.M. Angeliu, "Crack Tip Strain Rate: Estimates Based on Continuum Theory and Experimental Measurement", Corrosion/01, paper 131, NACE, Houston, TX (2001).
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Corrosion/01
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Young, L.M.1
Andresen, P.L.2
Angeliu, T.M.3
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23
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0033489090
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Stress corrosion crack propagation rate of alloy 600 in the primary water of pwr influence of a cold worked layer
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TMS, Warrendale, PA
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O. Raquet and G. Santarini, "Stress Corrosion Crack Propagation Rate of Alloy 600 in the Primary Water of PWR Influence of a Cold Worked Layer", 9th International Symposium on Environmental Degradation in Nuclear Power Systems-Water Reactors, TMS, Warrendale, PA (2000) 207-213.
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9th International Symposium on Environmental Degradation in Nuclear Power Systems-Water Reactors
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Raquet, O.1
Santarini, G.2
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24
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0033489282
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TMS, Warrendale, PA
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C. Amzallag, S.L., Hong, C. Pages and A. Gelpi, Stress Corrosion Life Assessment of Alloy 600 PWR Components, 9th International Symposium on Environmental Degradation in Nuclear Power Systems-Water Reactors, TMS, Warrendale, PA (2000) 243-250.
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(2000)
Stress Corrosion Life Assessment of Alloy 600 PWR Components, 9th International Symposium on Environmental Degradation in Nuclear Power Systems-Water Reactors
, pp. 243-250
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Amzallag S L, C.1
Pages, H.C.2
Gelpi, A.3
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25
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70349618076
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Stress corrosion crack growth in alloy 600 exposed to pwr and bwr environments
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paper 222, NACE, Houston, TX
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M.O. Speidel and R. Magdowski, "Stress Corrosion Crack Growth in Alloy 600 Exposed to PWR and BWR Environments", Corrosion/00, paper 222, NACE, Houston, TX (2000).
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Corrosion/00
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Speidel, M.O.1
Magdowski, R.2
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26
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85046717208
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Effects of dissolved oxygen, hydrogen and water purity on crack growth of boiling water reactor structural alloys in high temperature water
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October
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C.W. Jewett, "Effects of Dissolved Oxygen, Hydrogen and Water Purity on Crack Growth of Boiling Water Reactor Structural Alloys in High Temperature Water", GE Internal Report, NEDE-31618P, October 1988.
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(1988)
GE Internal Report, NEDE-31618P
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Jewett, C.W.1
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27
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78649377093
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Environmental degradation assessment and life prediction of nuclear piping made of stabilized austenitic stainless steel
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T. Shoji and T. Shibata, eds., NACE, Houston, TX
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M.O. Speidel and R. Magdowski, "Environmental Degradation Assessment and Life Prediction of Nuclear Piping Made of Stabilized Austenitic Stainless Steel" Proceedings of International Symposium on Plant Aging and Life Predictions of Corrodible Structures, T. Shoji and T. Shibata, eds., NACE, Houston, TX (1995) 951-956.
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(1995)
Proceedings of International Symposium on Plant Aging and Life Predictions of Corrodible Structures
, pp. 951-956
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Speidel, M.O.1
Magdowski, R.2
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