-
3
-
-
52349104237
-
-
Jones R.L., Gordon G.M., Neils G., H., Envrionmental Degradation of Materials in Boiling Water Reactors, Proc. 4th Int. Symp. Environmental Degradation Materials Nulcear Power Systems-Water Reactors, NACE, 1989, pp. 1-10.
-
Jones R.L., Gordon G.M., Neils G., H., "Envrionmental Degradation of Materials in Boiling Water Reactors", Proc. 4th Int. Symp. Environmental Degradation Materials Nulcear Power Systems-Water Reactors, NACE, 1989, pp. 1-10.
-
-
-
-
4
-
-
0033489379
-
Intergranular Stress Corrosion Cracking of Unsensitized Stainless Steels in BWR Environments
-
TMS
-
Angeliu T.M., Andresen P.L., Hall E., Sutliff J.A., Sitzman S., Horn R.M., "Intergranular Stress Corrosion Cracking of Unsensitized Stainless Steels in BWR Environments", Proc. 9th Int. Symp. Environmental Degradation Materials Nulcear Power Systems-Water Reactors. TMS, 1999. pp. 311-317.
-
(1999)
Proc. 9th Int. Symp. Environmental Degradation Materials Nulcear Power Systems-Water Reactors
, pp. 311-317
-
-
Angeliu, T.M.1
Andresen, P.L.2
Hall, E.3
Sutliff, J.A.4
Sitzman, S.5
Horn, R.M.6
-
5
-
-
7644228572
-
Progress in the Mechanistic Understanding of BWR SCC and Its Implication to the Prediction of SCC Growth Behavior in Plants
-
ANS
-
Shoji T., "Progress in the Mechanistic Understanding of BWR SCC and Its Implication to the Prediction of SCC Growth Behavior in Plants", Proc. 11th Int. Symp. Environmental Degradation Materials Nulcear Power Systems-Water Reactors, ANS, 2003, pp.588-598.
-
(2003)
Proc. 11th Int. Symp. Environmental Degradation Materials Nulcear Power Systems-Water Reactors
, pp. 588-598
-
-
Shoji, T.1
-
6
-
-
39149101029
-
-
Suzuki S., Kumagayi K., Shitara C., Mizutani J., Sakashita A., Tokuma H., Yamashita H., Maintenology, Vol. 3, 2004, pp.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
-
7
-
-
11044221216
-
Stress Corrosion of Sensitized and Quench Annealed type 304 Stainless steels in High Purity Water
-
paper No. 187
-
Agrawal A.K., Begley G.A., Staehle R.W., "Stress Corrosion of Sensitized and Quench Annealed type 304 Stainless steels in High Purity Water", Corroion/78, NACE, 1978, paper No. 187.
-
(1978)
Corroion/78, NACE
-
-
Agrawal, A.K.1
Begley, G.A.2
Staehle, R.W.3
-
8
-
-
0024105374
-
-
Ruther W.E., Soppet W.K., Kassner T.F., Corrosion, Vol.44, 1988, pp.791-799.
-
(1988)
Corrosion
, vol.44
, pp. 791-799
-
-
Ruther, W.E.1
Soppet, W.K.2
Kassner, T.F.3
-
9
-
-
0027659271
-
-
Andresen P.L., Corrosion, Vol. 49, 1993, pp. 714-725.
-
(1993)
Corrosion
, vol.49
, pp. 714-725
-
-
Andresen, P.L.1
-
10
-
-
0021539207
-
-
Weeks J.R., Vyas B., Isaacs H.S., Corrosion Science, Vol.25, 1985, pp.757-768.
-
(1985)
Corrosion Science
, vol.25
, pp. 757-768
-
-
Weeks, J.R.1
Vyas, B.2
Isaacs, H.S.3
-
12
-
-
39149118208
-
Effect of Temperature on Stress Corrosion Crack Growth in Austenitic Stainless Steels Exposed to Water
-
paper No. 291
-
Magdowski R., Speidel M.O., "Effect of Temperature on Stress Corrosion Crack Growth in Austenitic Stainless Steels Exposed to Water", Corrosion/90, NACE, 1990, paper No. 291.
-
(1990)
Corrosion/90, NACE
-
-
Magdowski, R.1
Speidel, M.O.2
-
14
-
-
85006422028
-
Corrosion/2001, NACE
-
paper No.228
-
Andresen P.L., Angeliu T.M., Young L.M., "Effect of Martensite and Hydrogen on SCC of Stainless Steels and Alloy 600", Corrosion/2001, NACE, 2001, paper No.228.
-
(2001)
-
-
Andresen, P.L.1
Angeliu, T.M.2
Young, L.M.3
-
15
-
-
0000514565
-
-
Mostovoy S., Crosley P.B., Ripling E.J., Journal of Materials, Vol.2, 1967, p.661.
-
(1967)
Journal of Materials
, vol.2
, pp. 661
-
-
Mostovoy, S.1
Crosley, P.B.2
Ripling, E.J.3
-
16
-
-
52349124709
-
-
Nakajima H., Shoji T., Kikuchi M., Nitsuma H., Shindo M., Detecting Acoustic Emission During Cyclic Crack Growth in Simulated BWR Environments. ASTMSTP 738. S. J. Hudak J, and R. J. Bucci, Eds., ASTM, 1981, p. 139.
-
Nakajima H., Shoji T., Kikuchi M., Nitsuma H., Shindo M., "Detecting Acoustic Emission During Cyclic Crack Growth in Simulated BWR Environments". ASTMSTP 738. S. J. Hudak J, and R. J. Bucci, Eds., ASTM, 1981, p. 139.
-
-
-
-
17
-
-
52349099425
-
Effects of Loading mode and temperature on stress corrosion cracking growth behavior of strain-hardened 316L stainless steels in oxygenated pure water
-
Lu Z.P., Shoji T., Takeda Y., Ito Y., Yamazaki S., Tsuchiya N., "Effects of Loading mode and temperature on stress corrosion cracking growth behavior of strain-hardened 316L stainless steels in oxygenated pure water". In: Proc. 13th Int. Symp. Environmental Degradation Materials Nulcear Power Systems-Water Reactors, 2007.
-
(2007)
Proc. 13th Int. Symp. Environmental Degradation Materials Nulcear Power Systems-Water Reactors
-
-
Lu, Z.P.1
Shoji, T.2
Takeda, Y.3
Ito, Y.4
Yamazaki, S.5
Tsuchiya, N.6
-
18
-
-
39149112683
-
SCC Growth Behavior of Cold Worked 316L Stainless Steel in Oxygenated Pure Water at different Temperatures
-
JSCE
-
Lu Z.P., Kai A., Ito Y., Takeda Y., Shoji T., "SCC Growth Behavior of Cold Worked 316L Stainless Steel in Oxygenated Pure Water at different Temperatures", Proc. 52nd Japan Conf. Materials and Environments. JSCE, 2005, p. 205.
-
(2005)
Proc. 52nd Japan Conf. Materials and Environments
, pp. 205
-
-
Lu, Z.P.1
Kai, A.2
Ito, Y.3
Takeda, Y.4
Shoji, T.5
-
19
-
-
0001829362
-
Theoretical prediction of SCC Growth BehaviorThreshold and Plateau Growth rate
-
NACE
-
Shoji T., Suzuki S., Ballinger R.G., "Theoretical prediction of SCC Growth BehaviorThreshold and Plateau Growth rate", Proc. 7th Int. Symp. Environmental Degradation Materials Nulcear Power Systems-Water Reactors. NACE, 1995, pp. 881-891.
-
(1995)
Proc. 7th Int. Symp. Environmental Degradation Materials Nulcear Power Systems-Water Reactors
, pp. 881-891
-
-
Shoji, T.1
Suzuki, S.2
Ballinger, R.G.3
-
20
-
-
84884720173
-
Probabilistic Interpretation of SCC Initiation and Growth
-
paper No.446
-
Andresen P.L., "Probabilistic Interpretation of SCC Initiation and Growth", Corrosion/99. NACE, 1999. paper No.446.
-
(1999)
Corrosion/99. NACE
-
-
Andresen, P.L.1
-
24
-
-
0001558008
-
-
Ford F.P., Corrosion, Vol.52, 1996, pp. 375-395.
-
(1996)
Corrosion
, vol.52
, pp. 375-395
-
-
Ford, F.P.1
-
25
-
-
43449088245
-
Understanding the Threshold Conditions for Stress Corrosion Cracking in Light Water Reactor Environments Based on the Deformation/Oxidation Mechanism
-
ASME, paper No. PVP2007-26183
-
Shoji T., Lu Z.P., Takeda Y., "Understanding the Threshold Conditions for Stress Corrosion Cracking in Light Water Reactor Environments Based on the Deformation/Oxidation Mechanism", ASME Pressure Vessels and Piping Division Conference (ASME PVP 2007/Creep8). ASME, 2007, paper No. PVP2007-26183.
-
(2007)
ASME Pressure Vessels and Piping Division Conference (ASME PVP 2007/Creep8)
-
-
Shoji, T.1
Lu, Z.P.2
Takeda, Y.3
|