-
1
-
-
0343622271
-
-
NUREG/CR-4092 (ORNL/TM-9491), Oak Ridge National Laboratory, Oak Ridge, Term.
-
W. J. Stelzman, R. G. Berggren, and T. N. Jones, Jr., ORNL Characterization of Heavy-Section Steel Technology Program Plates 01,02, and 03, NUREG/CR-4092 (ORNL/TM-9491), Oak Ridge National Laboratory, Oak Ridge, Term., 1985.
-
(1985)
ORNL Characterization of Heavy-Section Steel Technology Program Plates 01,02, and 03
-
-
Stelzman, W.J.1
Berggren, R.G.2
Jones T.N., Jr.3
-
2
-
-
0343186720
-
-
NUREG/CR-5913, (ORNL/TM-12156/V1), Oak Ridge National Laboratory, Oak Ridge, Tenn.
-
R. K. Nanstad, F. M. Haggag, D. E. McCabe, S. K. Iskander, K. O. Bowman, and B. H. Menke, Irradiation Effects on Fracture Toughness of Two High-Copper Submerged-Arc Welds, HSSI Series 5, NUREG/CR-5913, Vol. 1 (ORNL/TM-12156/V1), Oak Ridge National Laboratory, Oak Ridge, Tenn., 1992.
-
(1992)
Irradiation Effects on Fracture Toughness of Two High-Copper Submerged-Arc Welds, HSSI Series 5
, vol.1
-
-
Nanstad, R.K.1
Haggag, F.M.2
McCabe, D.E.3
Iskander, S.K.4
Bowman, K.O.5
Menke, B.H.6
-
3
-
-
0000405576
-
Ic Curves for High Copper Welds
-
N. H. Packan, R. E. Stoller, and A. S. Kumar, Eds., American Society for Testing and Materials, Philadelphia
-
Ic Curves for High Copper Welds," pp. 214-233 in Effects of Radiation on Materials: 14th International Symposium, ASTM STP 1046, N. H. Packan, R. E. Stoller, and A. S. Kumar, Eds., American Society for Testing and Materials, Philadelphia, 1990.
-
(1990)
Effects of Radiation on Materials: 14th International Symposium, ASTM STP 1046
, pp. 214-233
-
-
Nanstad, R.K.1
McCabe, D.E.2
Menke, B.H.3
Iskander, S.K.4
Haggag, F.M.5
-
4
-
-
0029307125
-
Charpy Impact Test Results on Five Materials and NIST Verification Specimens Using Instrumented 2-mm and 8-mm Strikers
-
T. A. Siewert and A. K. Schmieder, Eds., American Society for Testing and Materials, Philadelphia
-
R. K. Nanstad and M. A. Sokolov, "Charpy Impact Test Results on Five Materials and NIST Verification Specimens Using Instrumented 2-mm and 8-mm Strikers," pp. 111-139 in Pendulum Impact Machines: Procedures and Specimens for Verification, ASTM STP 1248, T. A. Siewert and A. K. Schmieder, Eds., American Society for Testing and Materials, Philadelphia, 1995.
-
(1995)
Pendulum Impact Machines: Procedures and Specimens for Verification, ASTM STP 1248
, pp. 111-139
-
-
Nanstad, R.K.1
Sokolov, M.A.2
-
5
-
-
0022241118
-
Analysis of Charpy V-Notch Impact Toughness of Irradiated A533-B Class 1 Plate and Four Submerged-Arc Welds
-
F. A. Garner and J. S. Perrin, Eds., American Society for Testing and Materials, Philadelphia
-
R. G. Berggren, J. R. Hawthorne, and R. K. Nanstad, "Analysis of Charpy V-Notch Impact Toughness of Irradiated A533-B Class 1 Plate and Four Submerged-Arc Welds," pp 1094-1110 in Effects of Radiation on Materials: 12th International Symposium, ASTM STP 870, F. A. Garner and J. S. Perrin, Eds., American Society for Testing and Materials, Philadelphia, 1985.
-
(1985)
Effects of Radiation on Materials: 12th International Symposium, ASTM STP 870
, pp. 1094-1110
-
-
Berggren, R.G.1
Hawthorne, J.R.2
Nanstad, R.K.3
-
6
-
-
0022241119
-
Effects of Neutron Irradiation on Fracture Toughness of A533-B Class 1 Plate and Four Submerged-Arc Welds
-
F. A. Garner and J. S. Perrin, Eds., American Society for Testing and Materials, Philadelphia
-
B. H. Menke, J. J. McGowan, R. G. Berggren, R. K. Nanstad, and K. C. Miller, "Effects of Neutron Irradiation on Fracture Toughness of A533-B Class 1 Plate and Four Submerged-Arc Welds," pp. 1111-1130 in Effects of Radiation on Materials: 12th International Symposium, ASTM STP 870, F. A. Garner and J. S. Perrin, Eds., American Society for Testing and Materials, Philadelphia, 1985.
-
(1985)
Effects of Radiation on Materials: 12th International Symposium, ASTM STP 870
, pp. 1111-1130
-
-
Menke, B.H.1
McGowan, J.J.2
Berggren, R.G.3
Nanstad, R.K.4
Miller, K.C.5
-
7
-
-
0343186719
-
-
ORNL/NRC/LTR-95/4, Oak Ridge National Laboratory, Oak Ridge, Tenn.
-
Jc and Charpy Curves: Analysis of Heavy-Section Steel Irradiation Program Data, ORNL/NRC/LTR-95/4, Oak Ridge National Laboratory, Oak Ridge, Tenn., 1995.
-
(1995)
Jc and Charpy Curves: Analysis of Heavy-Section Steel Irradiation Program Data
-
-
Sokolov, M.A.1
McCabe, D.E.2
-
8
-
-
0005552070
-
Radiation Embrittlement of Reactor Vessel Materials
-
Revision 2, U.S. Nuclear Regulatory Commission, Washington, D.C., May
-
Regulatory Guide 1.99, "Radiation Embrittlement of Reactor Vessel Materials," Revision 2, U.S. Nuclear Regulatory Commission, Washington, D.C., May 1988.
-
(1988)
Regulatory Guide 1.99
-
-
-
10
-
-
0343186706
-
Comparison of Fracture Toughness and Charpy Impact Properties Recovery by Thermal Annealing of Irradiated Reactor Pressure Vessel Steels
-
American Nuclear Society, La Grange Park, Ill.
-
M. A. Sokolov, D. E. McCabe, S. K. Iskander, and R. K. Nanstad, "Comparison of Fracture Toughness and Charpy Impact Properties Recovery by Thermal Annealing of Irradiated Reactor Pressure Vessel Steels," pp. 771-781 in 7th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Vol. 2, American Nuclear Society, La Grange Park, Ill., 1995.
-
(1995)
7th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, vol.2
, pp. 771-781
-
-
Sokolov, M.A.1
McCabe, D.E.2
Iskander, S.K.3
Nanstad, R.K.4
-
11
-
-
0033344234
-
Jc and Charpy Impact Toughness for Reactor Pressure Vessel Steels
-
R. K. Nanstad, M. L. Hamilton, F. A. Garner, and A. S. Kumar, Eds., American Society for Testing and Materials, West Conshohocken, Pa.
-
Jc and Charpy Impact Toughness for Reactor Pressure Vessel Steels," pp. 167-190 in Effects of Radiation on Materials, 18th International Symposium, ASTM STP 1325, R. K. Nanstad, M. L. Hamilton, F. A. Garner, and A. S. Kumar, Eds., American Society for Testing and Materials, West Conshohocken, Pa., 1999.
-
(1999)
Effects of Radiation on Materials, 18th International Symposium, ASTM STP 1325
, pp. 167-190
-
-
Sokolov, M.A.1
Nanstad, R.K.2
-
12
-
-
0027205754
-
Recovery of the Transition Temperature of Irradiated WWER-440 Vessel Metal by Annealing
-
L. E. Steele, Ed., American Society for Testing and Materials, Philadelphia
-
A. D. Amayev, A. M. Kryukov, and M. A. Sokolov, "Recovery of the Transition Temperature of Irradiated WWER-440 Vessel Metal by Annealing," pp. 369-379 in Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Fourth Volume), ASTM STP 1170, L. E. Steele, Ed., American Society for Testing and Materials, Philadelphia, 1993.
-
(1993)
Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Fourth Volume), ASTM STP 1170
, pp. 369-379
-
-
Amayev, A.D.1
Kryukov, A.M.2
Sokolov, M.A.3
-
13
-
-
0030217404
-
Effects of Annealing Time on the Recovery of Charpy V-Notch Properties of Irradiated High-Copper Weld Metal
-
D. S. Gelles, R. K. Nanstad, A. S. Kumar, and E. A. Little, Eds., American Society for Testing and Materials, Philadelphia
-
S. K. Iskander, M. A. Sokolov, and R. K. Nanstad, "Effects of Annealing Time on the Recovery of Charpy V-Notch Properties of Irradiated High-Copper Weld Metal," pp. 277-293 in Effects of Radiation on Materials: 17th International Symposium, ASTM STP 1270, D. S. Gelles, R. K. Nanstad, A. S. Kumar, and E. A. Little, Eds., American Society for Testing and Materials, Philadelphia, 1996.
-
(1996)
Effects of Radiation on Materials: 17th International Symposium, ASTM STP 1270
, pp. 277-293
-
-
Iskander, S.K.1
Sokolov, M.A.2
Nanstad, R.K.3
-
14
-
-
0005545602
-
Format and Content of Report for Thermal Annealing of Reactor Pressure Vessels
-
U.S. Nuclear Regulatory Commission, February
-
Regulatory Guide 1.162, "Format and Content of Report for Thermal Annealing of Reactor Pressure Vessels," U.S. Nuclear Regulatory Commission, February 1996.
-
(1996)
Regulatory Guide 1.162
-
-
-
15
-
-
0033335883
-
SANS Study of High-Copper RPV Welds in Irradiated and Annealed Conditions
-
R. K. Nanstad, M. L. Hamilton, F. A. Garner, and A. S. Kumar, Eds., American Society for Testing and Materials, West Conshohocken, Pa.
-
M. A. Sokolov, S. Spooner, G. R. Odette, B. D. Wirth, and G. E. Lucas, "SANS Study of High-Copper RPV Welds in Irradiated and Annealed Conditions," pp. 333-345 in Effects of Radiation on Materials, 18th International Symposium, ASTM STP 1325, R. K. Nanstad, M. L. Hamilton, F. A. Garner, and A. S. Kumar, Eds., American Society for Testing and Materials, West Conshohocken, Pa., 1999.
-
(1999)
Effects of Radiation on Materials, 18th International Symposium, ASTM STP 1325
, pp. 333-345
-
-
Sokolov, M.A.1
Spooner, S.2
Odette, G.R.3
Wirth, B.D.4
Lucas, G.E.5
-
16
-
-
0342317255
-
Exploratory Study of Irradiation, Annealing, and Reirradiation Effects on American and Russian Reactor Pressure Vessel Steels
-
American Nuclear Society, La Grange Park, Ill.
-
A. A. Chernobaeva, M A. Sokolov, R. K. Nanstad, A. M. Kryukov, Y. A. Nikolaev, and Yu. N. Korolev, "Exploratory Study of Irradiation, Annealing, and Reirradiation Effects on American and Russian Reactor Pressure Vessel Steels," pp. 871-882 in Proceedings of the Eighth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, August 10-14, 1997, Amelia Island, Florida, American Nuclear Society, La Grange Park, Ill., 1997.
-
(1997)
Proceedings of the Eighth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, August 10-14, 1997, Amelia Island, Florida
, pp. 871-882
-
-
Chernobaeva, A.A.1
Sokolov, M.A.2
Nanstad, R.K.3
Kryukov, A.M.4
Nikolaev, Y.A.5
Korolev, Yu.N.6
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