-
1
-
-
0033338807
-
Radiation-induced material changes and susceptibility to intergranular failure of light-water reactor core internals
-
in press
-
S. M. Bruemmer, E. P. Simonen, P. M. Scott, P. L. Andresen, G. S. Was and J. L. Nelson. "Radiation-Induced Material Changes and Susceptibility to Intergranular Failure of Light-Water Reactor Core Internals", J. of Nuclear Mater., 1999, in press.
-
(1999)
J. of Nuclear Mater.
-
-
Bruemmer, S.M.1
Simonen, E.P.2
Scott, P.M.3
Andresen, P.L.4
Was, G.S.5
Nelson, J.L.6
-
2
-
-
0028483357
-
A review of irradiation assisted stress corrosion cracking
-
P. Scott, "A Review of Irradiation Assisted Stress Corrosion Cracking", J. Nucl. Mater., 211 (1994), p. 101.
-
(1994)
J. Nucl. Mater.
, vol.211
, pp. 101
-
-
Scott, P.1
-
3
-
-
0028518292
-
Effects of irradiation on intergranular stress corrosion cracking
-
G. S. Was and S. M. Bruemmer, "Effects of Irradiation on Intergranular Stress Corrosion Cracking", J. Nucl. Mater., 216 (1994) 326-347.
-
(1994)
J. Nucl. Mater.
, vol.216
, pp. 326-347
-
-
Was, G.S.1
Bruemmer, S.M.2
-
4
-
-
0028518339
-
Microstructural and microchemical mechanisms controlling intergranular stress corrosion cracking in light water reactor systems
-
S. M. Bruemmer and G. S. Was, "Microstructural and Microchemical Mechanisms Controlling Intergranular Stress Corrosion Cracking in Light Water Reactor Systems", J. Nucl. Mater., 216 (1994) 348-363.
-
(1994)
J. Nucl. Mater.
, vol.216
, pp. 348-363
-
-
Bruemmer, S.M.1
Was, G.S.2
-
5
-
-
0031248584
-
Radiation hardening revisited: Role of intracascade clustering
-
B. N. Singh, A. J. Foreman and H. Trinkaus, "Radiation Hardening Revisited: Role of Intracascade Clustering", J. Nucl. Mater., 249 (1997), 103-115.
-
(1997)
J. Nucl. Mater.
, vol.249
, pp. 103-115
-
-
Singh, B.N.1
Foreman, A.J.2
Trinkaus, H.3
-
10
-
-
0002643002
-
Effects of minor elements on IASCC of type 316 model stainless steels
-
T. Tsukada, Y. Miwa, H. Nakajima and T. Kondo, "Effects of Minor Elements on IASCC of Type 316 Model Stainless Steels", Proc. 8th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, (1997), 795-802.
-
(1997)
Proc. 8th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 795-802
-
-
Tsukada, T.1
Miwa, Y.2
Nakajima, H.3
Kondo, T.4
-
11
-
-
0002264438
-
IASCC susceptibility of type 304, 304L, and 316L stainless steels
-
Y. Tanaka, S. Suzuki, K. Fukuya, H. Sakamoto, M. Kodama, S. Nishimura, K. Nakata and T. Kato, "IASCC Susceptibility of Type 304, 304L, and 316L Stainless Steels", Proc. 8th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, (1997), 803-811.
-
(1997)
Proc. 8th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 803-811
-
-
Tanaka, Y.1
Suzuki, S.2
Fukuya, K.3
Sakamoto, H.4
Kodama, M.5
Nishimura, S.6
Nakata, K.7
Kato, T.8
-
12
-
-
0012915382
-
An investigation into the origin and nature of the slope and X-axis intercept of the shear punch-tensile correlation using finite element analysis
-
in press
-
G. L. Hankin, R. G. Faulkner, M. A. Khaleel, M. L. Hamilton and M. B. Toloczko, "An Investigation into the Origin and Nature of the Slope and X-axis Intercept of the Shear Punch-Tensile Correlation Using Finite Element Analysis" Proc. of the 19th ASTM Int. Symposium on Effects of Radiation on Materials, STP 1366, in press.
-
Proc. of the 19th ASTM Int. Symposium on Effects of Radiation on Materials, STP 1366
-
-
Hankin, G.L.1
Faulkner, R.G.2
Khaleel, M.A.3
Hamilton, M.L.4
Toloczko, M.B.5
-
13
-
-
85088716918
-
Neutron-induced evolution of mechanical properties of 20% cold-worked 316 stainless steel as observed in both miniature tensile and TEM shear punch specimens
-
in press
-
M. L. Hamilton, F. A. Garner, G. L. Hankin, R. G. Faulkner and M. B. Toloczko, "Neutron-Induced Evolution of Mechanical Properties of 20% Cold-Worked 316 Stainless Steel as Observed in Both Miniature Tensile and TEM Shear Punch Specimens", Proc. of the 19th ASTM Int. Symposium on Effects of Radiation on Materials, STP 1366, in press.
-
Proc. of the 19th ASTM Int. Symposium on Effects of Radiation on Materials, STP 1366
-
-
Hamilton, M.L.1
Garner, F.A.2
Hankin, G.L.3
Faulkner, R.G.4
Toloczko, M.B.5
-
14
-
-
4244072907
-
Local evolution of microstructure and microchemistry near grain boundaries in irradiated austenitic stainless steels
-
these proceedings
-
E. S. Simonen, D. J. Edwards and S. M. Bruemmer, "Local Evolution of Microstructure and Microchemistry Near Grain Boundaries in Irradiated Austenitic Stainless Steels", these proceedings.
-
-
-
Simonen, E.S.1
Edwards, D.J.2
Bruemmer, S.M.3
-
15
-
-
0000894437
-
Effects of austenite stability on sensitization to irradiation assisted stress corrosion
-
A. Jensen, L. Ljungberg, K. Pettersson, and J. Walmsley, "Effects of Austenite Stability on Sensitization to Irradiation Assisted Stress Corrosion", Proc. 8th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, (1997), 785-794
-
(1997)
Proc. 8th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 785-794
-
-
Jensen, A.1
Ljungberg, L.2
Pettersson, K.3
Walmsley, J.4
-
16
-
-
0344371667
-
Deformation temperature, strain rate, and irradiation microstructures effects on localized plasticity in 304L SS
-
J. I. Cole, J. L. Brimhall, J. S. Vetrano and S. M. Bruemmer, "Deformation Temperature, Strain Rate, and Irradiation Microstructures Effects on Localized Plasticity in 304L SS", Proc. 7th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, (1996), 817-827.
-
(1996)
Proc. 7th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 817-827
-
-
Cole, J.I.1
Brimhall, J.L.2
Vetrano, J.S.3
Bruemmer, S.M.4
-
18
-
-
0013016932
-
-
D.J. Edwards, B.N. Singh, P. Toft and M. Eldrup, to be presented at 9th International Symposium on Fusion Reactor Materials to held in Colorado Springs, CO, Oct. 10-15, 1999.
-
9th International Symposium on Fusion Reactor Materials to Held in Colorado Springs, CO, Oct. 10-15, 1999
-
-
Edwards, D.J.1
Singh, B.N.2
Toft, P.3
Eldrup, M.4
|