-
1
-
-
0342823710
-
Core demonstration experiment: A liquid metal reactor core demonstration experiment using HT9
-
Ethridge, J. L., and Walter, A. E., "Core Demonstration Experiment: A Liquid Metal Reactor Core Demonstration Experiment Using HT9", Transactions of the American Nuclear Society, vol. 60, 1989, pp. 286-287.
-
(1989)
Transactions of the American Nuclear Society
, vol.60
, pp. 286-287
-
-
Ethridge, J.L.1
Walter, A.E.2
-
2
-
-
26544456315
-
Advanced liquid metal reactor fuel and blanket designs using HT9
-
Kyoto, Japan, Atomic Energy Society of Japan
-
Bridges, A. E., Walter, A. E., Leggett. R. D., Baker, R. B., and Gneiting, B. C., "Advanced Liquid Metal Reactor Fuel and Blanket Designs Using HT9", Proceedings of the International Conference on Fast Reactor and Related Fuel Cycles, Kyoto, Japan, Vol. II, Atomic Energy Society of Japan, 1991, pp. P1.21.1 - P1.21.10.
-
(1991)
Proceedings of the International Conference on Fast Reactor and Related Fuel Cycles
, vol.2
-
-
Bridges, A.E.1
Walter, A.E.2
Leggett, R.D.3
Baker, R.B.4
Gneiting, B.C.5
-
3
-
-
0027658819
-
Status of fuel, blanket, and absorber testing in the fast flux test facility
-
Baker, R. B., Bard, F. E., Leggett, R. D., and Pitner, A. L., "Status of Fuel, Blanket, and Absorber Testing in the Fast Flux Test Facility", Journal of Nuclear Materials, Vol. 204, 1993, pp. 109-118.
-
(1993)
Journal of Nuclear Materials
, vol.204
, pp. 109-118
-
-
Baker, R.B.1
Bard, F.E.2
Leggett, R.D.3
Pitner, A.L.4
-
4
-
-
0030263472
-
Irradiation creep and void swelling of two LMR heats of HT9 at ∼400°C and 165 dpa
-
Toloczko, M. B., and Garner, F. A., "Irradiation Creep and Void Swelling of Two LMR Heats of HT9 at ∼400°C and 165 dpa", Journal of Nuclear Materials, Vol. 233-237, 1996, pp. 289-292.
-
(1996)
Journal of Nuclear Materials
, vol.233-237
, pp. 289-292
-
-
Toloczko, M.B.1
Garner, F.A.2
-
5
-
-
0028320696
-
The influence of specimen size on measurement of thermal or irradiation creep in pressurized tubes
-
ASTM STP 1175, A. S. Kumar, D. S. Gelles, R. K. Nanstad, and E. A. Little, Editors, American Society for Testing and Materials, Philadelphia
-
Garner, F. A., Hamilton, M. L., Puigh, R. J., Eiholzer, C. R., Duncan, D. R., Toloczko, M. B., and Kumar, A. S., "The Influence of specimen Size on Measurement of Thermal or Irradiation Creep in Pressurized Tubes", Effects of Radiation on Materials: 16th International Symposium, ASTM STP 1175, A. S. Kumar, D. S. Gelles, R. K. Nanstad, and E. A. Little, Editors, American Society for Testing and Materials, Philadelphia, 1993, pp. 631-645.
-
(1993)
Effects of Radiation on Materials: 16th International Symposium
, pp. 631-645
-
-
Garner, F.A.1
Hamilton, M.L.2
Puigh, R.J.3
Eiholzer, C.R.4
Duncan, D.R.5
Toloczko, M.B.6
Kumar, A.S.7
-
6
-
-
0019684674
-
Irradiated materials measurement technology
-
ASTM STP 725, American Society for Testing and Materials
-
Gilbert, E. R., and Chin, B. A., "Irradiated Materials Measurement Technology", Effects of Radiation on Materials, 10th Conference, ASTM STP 725, American Society for Testing and Materials, 1981, pp. 665-679.
-
(1981)
Effects of Radiation on Materials, 10th Conference
, pp. 665-679
-
-
Gilbert, E.R.1
Chin, B.A.2
-
7
-
-
17544399538
-
Determination of the creep compliance and creep-swelling coupling coefficient for neutron irradiated titanium-modified stainless steels at ∼400°C
-
Toloczko, M. B., Garner, F. A., and Eiholzer, C. R., "Determination of the Creep Compliance and Creep-Swelling Coupling Coefficient for Neutron Irradiated Titanium-Modified Stainless Steels at ∼400°C", Journal of Nuclear Materials, Vol. 191-194, 1992, pp. 803-807.
-
(1992)
Journal of Nuclear Materials
, vol.191-194
, pp. 803-807
-
-
Toloczko, M.B.1
Garner, F.A.2
Eiholzer, C.R.3
-
8
-
-
0028495930
-
Relationship between swelling and irradiation creep in cold-worked PCA stainless steel irradiated to ∼178 dpa at ∼400°C
-
Toloczko, M. B., and Garner, F. A., "Relationship Between Swelling and Irradiation Creep in Cold-worked PCA Stainless Steel Irradiated to ∼178 dpa at ∼400°C", Journal of Nuclear Materials, Vol. 212-215, 1994, pp. 509-513.
-
(1994)
Journal of Nuclear Materials
, vol.212-215
, pp. 509-513
-
-
Toloczko, M.B.1
Garner, F.A.2
-
9
-
-
0024035646
-
Irradiation creep and swelling of AISI 316 exposures of 130 dpa at 385-400°C
-
Garner, F. A., and Porter, D. L., "Irradiation Creep and Swelling of AISI 316 Exposures of 130 dpa at 385-400°C", Journal of Nuclear Materials, Vol. 155-157, 1988, pp. 1006-1013.
-
(1988)
Journal of Nuclear Materials
, vol.155-157
, pp. 1006-1013
-
-
Garner, F.A.1
Porter, D.L.2
-
10
-
-
0028494741
-
Irradiation creep and swelling of the US fusion heats of HT9 and 9Cr-1Mo to 208 dpa at ∼400°C
-
Toloczko, M. B., Garner, F. A., and Eiholzer, C. R., "Irradiation Creep and Swelling of the US Fusion heats of HT9 and 9Cr-1Mo to 208 dpa at ∼400°C", Journal of Nuclear Materials, Vol. 212-215, 1994, pp. 604-607.
-
(1994)
Journal of Nuclear Materials
, vol.212-215
, pp. 604-607
-
-
Toloczko, M.B.1
Garner, F.A.2
Eiholzer, C.R.3
-
12
-
-
0027042837
-
Behavior under neutron irradiation of the 15-15Ti and EM10 steels used as standard materials of the Phenix fuel subassembly
-
ASTM STP 1125, American Society for Testing and Materials
-
Seran, J. L., Levy, V. Dubuisson, P., Gilbon D., Maillard, A., Fissolo, A., Touron, H., Cauvin, R., Chalony, A., and Le Boulbin, E., "Behavior Under Neutron Irradiation of the 15-15Ti and EM10 Steels Used as Standard Materials of the Phenix Fuel Subassembly", Effects of Radiation on Materials, 15th International Symposium, ASTM STP 1125, American Society for Testing and Materials, 1992, pp. 1209-1233.
-
(1992)
Effects of Radiation on Materials, 15th International Symposium
, pp. 1209-1233
-
-
Seran, J.L.1
Levy, V.2
Dubuisson, P.3
Gilbon, D.4
Maillard, A.5
Fissolo, A.6
Touron, H.7
Cauvin, R.8
Chalony, A.9
Le Boulbin, E.10
-
13
-
-
85069421156
-
Irradiation creep at temperatures of 400°C and below for application to near term fusion devices
-
R. K. Nanstad, M. L. Hamilton, F. A. Garner, and A. S. Kumar, Eds., American Society for Testing and Materials
-
Grossbeck, M. L., Gibson, L. T., and Jitsukawa, S. "Irradiation Creep at Temperatures of 400°C and Below for Application to Near Term Fusion Devices", 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, 1998.
-
(1998)
Effects of Radiation on Materials: 18th International Symposium, ASTM STP 1325
-
-
Grossbeck, M.L.1
Gibson, L.T.2
Jitsukawa, S.3
-
15
-
-
0021371448
-
Irradiation creep due to elastodiffusion
-
Woo, C. H., "Irradiation Creep Due to Elastodiffusion", Journal of Nuclear Materials, Vol. 120, 1984, pp. 55-64.
-
(1984)
Journal of Nuclear Materials
, vol.120
, pp. 55-64
-
-
Woo, C.H.1
-
16
-
-
0024087869
-
Theory of irradiation deformation in non-cubic metals: Effects of anisotropic diffusion
-
Woo, C. H., "Theory of Irradiation Deformation in Non-Cubic Metals: Effects of Anisotropic Diffusion", Journal of Nuclear Materials, Vol. 159, 1988, pp. 237-256.
-
(1988)
Journal of Nuclear Materials
, vol.159
, pp. 237-256
-
-
Woo, C.H.1
-
17
-
-
0024088046
-
Irradiation creep models - An overview
-
Matthews, J. R., and Finnis, M. W., "Irradiation Creep Models - an Overview", Journal of Nuclear Materials, Vol. 159, 1988, pp. 257-285.
-
(1988)
Journal of Nuclear Materials
, vol.159
, pp. 257-285
-
-
Matthews, J.R.1
Finnis, M.W.2
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