-
1
-
-
0028256790
-
The modeling of radiation hardening and embrittlement in magnox mild steel submerged-arc welds
-
Gelles, D.S., Nanstead, R.K., Little, E.A. (Eds.), ASTM STP 1175, American Society for Testing and Materials, Philadelphia, PA
-
Buswell, J.T., Jones, R.B., 1993. The modeling of radiation hardening and embrittlement in magnox mild steel submerged-arc welds. In: Gelles, D.S., Nanstead, R.K., Little, E.A. (Eds.), The Effects of Radiation on Materials: 16th International Symposium, ASTM STP 1175, American Society for Testing and Materials, Philadelphia, PA, p. 424.
-
(1993)
The Effects of Radiation on Materials: 16th International Symposium
, pp. 424
-
-
Buswell, J.T.1
Jones, R.B.2
-
2
-
-
0005603969
-
-
NUREG/CR-6327
-
Eason, E.D., Wright, J.E., Nelson, E.E., Odette, G.R., Mader, E.V., 1995. Embrittlement recovery due to annealing of reactor pressure vessel steels. NUREG/CR-6327.
-
(1995)
Embrittlement Recovery Due to Annealing of Reactor Pressure Vessel Steels
-
-
Eason, E.D.1
Wright, J.E.2
Nelson, E.E.3
Odette, G.R.4
Mader, E.V.5
-
4
-
-
0348085408
-
The BR3 pressure vessel anneal: Lessons and perspective
-
Albuquerque, New Mexico
-
Fabry, A., 1994. The BR3 pressure vessel anneal: lessons and perspective. Reactor Pressure Vessel Thermal Annealing Workshop, Albuquerque, New Mexico.
-
(1994)
Reactor Pressure Vessel Thermal Annealing Workshop
-
-
Fabry, A.1
-
6
-
-
0003964042
-
-
PhD Thesis, Department of Materials, University of California, Santa Barbara, CA
-
Mader, E.V., 1995. Kinetics of irradiation embrittlement and post-irradiation annealing of nuclear reactor pressure vessel steels. PhD Thesis, Department of Materials, University of California, Santa Barbara, CA.
-
(1995)
Kinetics of Irradiation Embrittlement and Post-irradiation Annealing of Nuclear Reactor Pressure Vessel Steels
-
-
Mader, E.V.1
-
7
-
-
0346194043
-
Feasibility of a methodology for thermal annealing an embrittled reactor vessel
-
Electric Power Research Institute
-
Mager, T.R. Lott, R.G., 1989. Feasibility of a methodology for thermal annealing an embrittled reactor vessel. EPRI Report NP-6113-M, Electric Power Research Institute.
-
(1989)
EPRI Report NP-6113-M
-
-
Mager, T.R.1
Lott, R.G.2
-
8
-
-
0022205642
-
Post-irradiation annealing recovery of commercial pressure vessel steels, effects of radiation on materials
-
Garner, F.A., Perrin, J.S. (Eds.), ASTM STP 870, American Society for Testing and Materials, Philadelphia
-
Macdonald, B., 1985. Post-irradiation annealing recovery of commercial pressure vessel steels, effects of radiation on materials. In: Garner, F.A., Perrin, J.S. (Eds.), Twelfth International Symposium. ASTM STP 870, American Society for Testing and Materials, Philadelphia, pp. 972-978.
-
(1985)
Twelfth International Symposium
, pp. 972-978
-
-
Macdonald, B.1
-
11
-
-
0029218505
-
Radiation induced microstructural evolution in reactor pressure vessel steels
-
Robertson, et al. (Eds.), Microstructures of Irradiated Materials, I. MRS, Pittsburgh
-
Odette, G.R., 1995. Radiation induced microstructural evolution in reactor pressure vessel steels. In: Robertson, et al. (Eds.), Microstructures of Irradiated Materials, MRS Symposium Proceedings 373, I. MRS, Pittsburgh, p. 137.
-
(1995)
MRS Symposium Proceedings
, vol.373
, pp. 137
-
-
Odette, G.R.1
-
13
-
-
49949127799
-
Critique of in-place annealing of SM-1A nuclear reactor vessel
-
Paper 67-WA/ER-3, 1967
-
Potapovs, U., G.W. Knighton, A.S. Denton, 1967. Critique of in-place annealing of SM-1A nuclear reactor vessel, Am. Soc. Mechanical Eng., Paper 67-WA/ER-3, 1967; also, Nucl. Eng. Des. 8, 1968, 39-57.
-
(1967)
Am. Soc. Mechanical Eng.
-
-
Potapovs, U.1
Knighton, G.W.2
Denton, A.S.3
-
14
-
-
49949127799
-
-
Potapovs, U., G.W. Knighton, A.S. Denton, 1967. Critique of in-place annealing of SM-1A nuclear reactor vessel, Am. Soc. Mechanical Eng., Paper 67-WA/ER-3, 1967; also, Nucl. Eng. Des. 8, 1968, 39-57.
-
(1968)
Nucl. Eng. Des.
, vol.8
, pp. 39-57
-
-
-
16
-
-
0005574882
-
-
NUREG/ CR-6076
-
Stallman, F.W., Wang, J.A., Kam, F.B.K., 1994. TR-EDB: Test reactor embrittlement data base, Version 1, NUREG/ CR-6076.
-
(1994)
TR-EDB: Test Reactor Embrittlement Data Base, Version 1
-
-
Stallman, F.W.1
Wang, J.A.2
Kam, F.B.K.3
-
17
-
-
0347455451
-
Format and content of application for approval for thermal annealing of reactor pressure vessels
-
US NRC, 1994. Format and content of application for approval for thermal annealing of reactor pressure vessels. Draft Regulatory Guide DG-1027.
-
(1994)
Draft Regulatory Guide DG-1027
-
-
-
18
-
-
0030217396
-
Electron microscopy and small angle neutron scattering study of precipitates in low-alloy submerged-arc welds
-
Gelles, D.S., Nanstead, R.K., Kumar, A.V., Little, E.A. (Eds.), ASTM STP 1270, American Society for Testing and Materials, West Conshohoken, PA, 19428-2959
-
Williams, T.J., Phythian, P.J., 1996. Electron microscopy and small angle neutron scattering study of precipitates in low-alloy submerged-arc welds. In: Gelles, D.S., Nanstead, R.K., Kumar, A.V., Little, E.A. (Eds.), Effects of Irradiation on Materials: 17th International Symposium, ASTM STP 1270, American Society for Testing and Materials, West Conshohoken, PA, 19428-2959, p. 191.
-
(1996)
Effects of Irradiation on Materials: 17th International Symposium
, pp. 191
-
-
Williams, T.J.1
Phythian, P.J.2
|