-
2
-
-
39749199575
-
-
P.M. Scott, C. Benhamou, An overview of recent obervation and interpretation of IGSCC in nickel base alloys in PWR primary water, in: Proc. of the 10th Int. Symp. Environmental Degradation Materials Nuclear Power Systems-Water Reactors. NACE, 2001, CDROM.
-
P.M. Scott, C. Benhamou, An overview of recent obervation and interpretation of IGSCC in nickel base alloys in PWR primary water, in: Proc. of the 10th Int. Symp. Environmental Degradation Materials Nuclear Power Systems-Water Reactors. NACE, 2001, CDROM.
-
-
-
-
3
-
-
39749089979
-
-
P.M. Scott, P. Combrade, On the mechanism of stress corrosion crack initiation and growth in Alloy 600 exposed to PWR primary water, in: Proc. of the 11th Int. Symp. Environmental Degradation Materials Nuclear Power Systems-Water Reactors. ANS, 2003, pp. 29-38.
-
P.M. Scott, P. Combrade, On the mechanism of stress corrosion crack initiation and growth in Alloy 600 exposed to PWR primary water, in: Proc. of the 11th Int. Symp. Environmental Degradation Materials Nuclear Power Systems-Water Reactors. ANS, 2003, pp. 29-38.
-
-
-
-
4
-
-
0033489488
-
-
C. Amzallag, F. Vaillant, Stress corrosion cracking propagation rates in reactor vessel head penetrations in Alloy 600, in: Proc. 9th Int. Symp. Environ. Degradation of Materials Nuclear Power Systems-Water Reactors, TMS, 1999, pp. 235-241.
-
C. Amzallag, F. Vaillant, Stress corrosion cracking propagation rates in reactor vessel head penetrations in Alloy 600, in: Proc. 9th Int. Symp. Environ. Degradation of Materials Nuclear Power Systems-Water Reactors, TMS, 1999, pp. 235-241.
-
-
-
-
6
-
-
39749149713
-
-
R. Magdowski, F. Vaillant, C. Amzallag, M.O. Speidel, Stress corrosion crack growth rates of Alloy 600 in simulated PWR coolant, in: Proc. 8th Int. Symp. Environ. Degradation of Materials Nuclear Power Systems-Water Reactors, ANS, 1997, pp. 333-338.
-
R. Magdowski, F. Vaillant, C. Amzallag, M.O. Speidel, Stress corrosion crack growth rates of Alloy 600 in simulated PWR coolant, in: Proc. 8th Int. Symp. Environ. Degradation of Materials Nuclear Power Systems-Water Reactors, ANS, 1997, pp. 333-338.
-
-
-
-
8
-
-
39749143357
-
-
MRP-55NP, Materials Reliability Program (MRP) Crack Growth Rates for Evaluating Primary Water Stress Corrosion Cracking (PWSCC) of Thick-wall Alloy 600 Materials, Revision 1, EPRI, Palo Alto, CA: 2002. 1006695-NP.
-
MRP-55NP, Materials Reliability Program (MRP) Crack Growth Rates for Evaluating Primary Water Stress Corrosion Cracking (PWSCC) of Thick-wall Alloy 600 Materials, Revision 1, EPRI, Palo Alto, CA: 2002. 1006695-NP.
-
-
-
-
9
-
-
39749118086
-
-
G.A. Young, N. Lewis, D.S. Morton, The stress corrosion crack growth rate of Alloy 600 heat affected zones exposed to high purity water. Proc. Conference on Vessel Head Penetration Inspection, Cracking and Repairs. USNRC, 2003, pp. 309-335.
-
G.A. Young, N. Lewis, D.S. Morton, The stress corrosion crack growth rate of Alloy 600 heat affected zones exposed to high purity water. Proc. Conference on Vessel Head Penetration Inspection, Cracking and Repairs. USNRC, 2003, pp. 309-335.
-
-
-
-
10
-
-
39749144577
-
-
OIM Analysis for Windows, User Manual. TexSEM laboratories, Inc., Utah, USA, 2002.
-
OIM Analysis for Windows, User Manual. TexSEM laboratories, Inc., Utah, USA, 2002.
-
-
-
-
12
-
-
85167864022
-
Detecting acoustic emission during cyclic crack growth in simulated BWR environments
-
Hudak S.J., and Bucci R.J. (Eds), ASTM
-
Nakajima H., Shoji T., Kikuchi M., Nitsuma H., and Shindo M. Detecting acoustic emission during cyclic crack growth in simulated BWR environments. In: Hudak S.J., and Bucci R.J. (Eds). ASTM STP vol. 738 (1981), ASTM 139
-
(1981)
ASTM STP
, vol.738
, pp. 139
-
-
Nakajima, H.1
Shoji, T.2
Kikuchi, M.3
Nitsuma, H.4
Shindo, M.5
-
14
-
-
39749150486
-
-
S. Yamazaki, Z.P. Lu, Y. Ito, Y. Takeda, T. Shoji, Effects of material factors on stress corrosion cracking growth in the heat affected zones of austenitic alloy weldments, in: Proc. Asia Pacific Symp. Corrosion Nuclear System., JSCE, 2007, paper No. B102.
-
S. Yamazaki, Z.P. Lu, Y. Ito, Y. Takeda, T. Shoji, Effects of material factors on stress corrosion cracking growth in the heat affected zones of austenitic alloy weldments, in: Proc. Asia Pacific Symp. Corrosion Nuclear System., JSCE, 2007, paper No. B102.
-
-
-
-
15
-
-
70349618076
-
-
M.O. Speidel, R. Magdowski, Stress corrosion crack growth in Alloy 600 exposed to PWR and BWR environments. NACE, 2000, paper No. 222.
-
M.O. Speidel, R. Magdowski, Stress corrosion crack growth in Alloy 600 exposed to PWR and BWR environments. NACE, 2000, paper No. 222.
-
-
-
-
17
-
-
0027888149
-
-
T.B. Cassagne, A. Gelpi, Crack growth rate measurements on alloy 600 steam generator tubing in primary and hydrogenated AVT water, in: Proc. 6th Int. Symp. Environ. Degradation of Materials Nuclear Power Systems-Water Reactors, TMS, 1993, pp. 679-686.
-
T.B. Cassagne, A. Gelpi, Crack growth rate measurements on alloy 600 steam generator tubing in primary and hydrogenated AVT water, in: Proc. 6th Int. Symp. Environ. Degradation of Materials Nuclear Power Systems-Water Reactors, TMS, 1993, pp. 679-686.
-
-
-
-
20
-
-
39749089377
-
-
F. Vaillant, C. Amzallag, J. Champredonde, Crack growth rate measurements of Alloy 600 vessel head penetrations, in: Proc. 8th Inter. Symp. Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, ANS, 1997, pp.357-365.
-
F. Vaillant, C. Amzallag, J. Champredonde, Crack growth rate measurements of Alloy 600 vessel head penetrations, in: Proc. 8th Inter. Symp. Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, ANS, 1997, pp.357-365.
-
-
-
-
24
-
-
39749116304
-
-
T. Shoji, S. Suzuki, R.G. Ballinger, Theoretical prediction of SCC growth behavior-threshold and plateau growth rate, in: Proc. 7th Int. Symp. Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, NACE, 1995, pp. 881-891.
-
T. Shoji, S. Suzuki, R.G. Ballinger, Theoretical prediction of SCC growth behavior-threshold and plateau growth rate, in: Proc. 7th Int. Symp. Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, NACE, 1995, pp. 881-891.
-
-
-
-
25
-
-
39749136595
-
-
T. Shoji, Z.P. Lu, Y. Takeda, Understanding the Threshold Conditions for Stress Corrosion Cracking in Light Water Reactor Environments Based on the Deformation/ Oxidation Mechanism. ASME PVP 2007/Creep8, ASME, 2007, Paper No. PVP2007-26183.
-
T. Shoji, Z.P. Lu, Y. Takeda, Understanding the Threshold Conditions for Stress Corrosion Cracking in Light Water Reactor Environments Based on the Deformation/ Oxidation Mechanism. ASME PVP 2007/Creep8, ASME, 2007, Paper No. PVP2007-26183.
-
-
-
-
27
-
-
33745192601
-
-
E.D. Eason, R. Pathania, T. Shoji. Evaluation of the Fracture Research Institute theoretical stress corrosion cracking model, in: Proc. of the 12th Int. Symp. Environmental Degradation Materials Nulcear Power Systems-Water Reactors. TMS, 2005, pp. 145-154.
-
E.D. Eason, R. Pathania, T. Shoji. Evaluation of the Fracture Research Institute theoretical stress corrosion cracking model, in: Proc. of the 12th Int. Symp. Environmental Degradation Materials Nulcear Power Systems-Water Reactors. TMS, 2005, pp. 145-154.
-
-
-
-
28
-
-
39749178455
-
-
J.R. Rice, Mechanics Aspects of Stress Corrosion Cracking and Hydrogen Embrittlement, in: R.W. Staehle et al., (Eds.), Proc. Stress Corrosion Cracking and Hydrogen Embrittlement of Iron Base Alloys. Staehle, NACE, 1977, pp. 11-15
-
J.R. Rice, Mechanics Aspects of Stress Corrosion Cracking and Hydrogen Embrittlement, in: R.W. Staehle et al., (Eds.), Proc. Stress Corrosion Cracking and Hydrogen Embrittlement of Iron Base Alloys. Staehle, NACE, 1977, pp. 11-15
-
-
-
-
29
-
-
39749164156
-
-
T. Shoji, Progress in the mechanistic understanding of BWR SCC and its implication to the prediction of SCC growth behavior in plants, in; Proc. 11th Int. Symp. Environmental Degradation Materials Nulcear Power Systems-Water Reactors, ANS, 2003, pp. 588-598.
-
T. Shoji, Progress in the mechanistic understanding of BWR SCC and its implication to the prediction of SCC growth behavior in plants, in; Proc. 11th Int. Symp. Environmental Degradation Materials Nulcear Power Systems-Water Reactors, ANS, 2003, pp. 588-598.
-
-
-
-
30
-
-
39149101029
-
-
Suzuki S., Kumagayi K., Shitara C., Mizutani J., Sakashita A., Tokuma H., and Yamashita H. Maintenology 3 (2004) 65-70
-
(2004)
Maintenology
, vol.3
, pp. 65-70
-
-
Suzuki, S.1
Kumagayi, K.2
Shitara, C.3
Mizutani, J.4
Sakashita, A.5
Tokuma, H.6
Yamashita, H.7
|