-
1
-
-
0040111280
-
Performance of Failed BWR Fuel
-
West Palm Beach, FL, 17-21 April American Nuclear Society
-
Armijo, J. S., "Performance of Failed BWR Fuel," Proceedings of the 1994 International Topical Meeting on Light Water Reactor Fuel Performance, West Palm Beach, FL, 17-21 April 1994, American Nuclear Society, pp. 410-422.
-
(1994)
Proceedings of the 1994 International Topical Meeting on Light Water Reactor Fuel Performance
, pp. 410-422
-
-
Armijo, J.S.1
-
2
-
-
0020292725
-
-
IWGFPT-6
-
Davies, J. H., "Secondary Damage in LWR Fuel Following PCI Detection - Characteristics and Mechanisms," IWGFPT-6, 1980, pp. 135-140: IAEA Specialists Meeting on Behavior of Defected Zirconium Alloy Clad Ceramic Fuel in Water Cooled Reactors, Chalk River, Ontario, Canada, 17- 20 Sept. 1979, Transaction of the American Nuclear Society, 1982, pp. 269-270.
-
(1980)
Secondary Damage in LWR Fuel Following PCI Detection - Characteristics and Mechanisms
, pp. 135-140
-
-
Davies, J.H.1
-
3
-
-
0342384303
-
IAEA Specialists Meeting on Behavior of Defected Zirconium Alloy Clad Ceramic Fuel in Water Cooled Reactors
-
Chalk River, Ontario, Canada, 17-20 Sept. 1979
-
Davies, J. H., "Secondary Damage in LWR Fuel Following PCI Detection - Characteristics and Mechanisms," IWGFPT-6, 1980, pp. 135-140: IAEA Specialists Meeting on Behavior of Defected Zirconium Alloy Clad Ceramic Fuel in Water Cooled Reactors, Chalk River, Ontario, Canada, 17-20 Sept. 1979, Transaction of the American Nuclear Society, 1982, pp. 269-270.
-
(1982)
Transaction of the American Nuclear Society
, pp. 269-270
-
-
-
4
-
-
0001591560
-
Internal Hydriding in Irradiated Defected Zircaloy Fuel Rods
-
L. F. P. Swam and C. M. Euken, Eds., American Society for Testing and Materials, Philadelphia
-
Clayton, J. H., "Internal Hydriding in Irradiated Defected Zircaloy Fuel Rods," Zirconium in the Nuclear Industry: Eighth International Symposium, ASTM STP 1023, L. F. P. Swam and C. M. Euken, Eds., American Society for Testing and Materials, Philadelphia, 1989, pp. 266-288.
-
(1989)
Zirconium in the Nuclear Industry: Eighth International Symposium, ASTM STP 1023
, pp. 266-288
-
-
Clayton, J.H.1
-
5
-
-
0343689460
-
Post-Irradiation Examination of Failed KKL Fuel Rods
-
Karlsruhe, Germany, 29-30 Nov.
-
Davies, J. H. and Armijo, J. S., "Post-Irradiation Examination of Failed KKL Fuel Rods," KTG Fuel Conference, Karlsruhe, Germany, 29-30 Nov. 1993.
-
(1993)
KTG Fuel Conference
-
-
Davies, J.H.1
Armijo, J.S.2
-
6
-
-
0032155822
-
Combined Effects of Radiation Damage and Hydrides on the Ductility of Zircaloy-2
-
Wisner, S. B. and Adamson, R. B., "Combined Effects of Radiation Damage and Hydrides on the Ductility of Zircaloy-2," Nuclear Engineering and Design, Vol. 185, 1998, pp. 33-49.
-
(1998)
Nuclear Engineering and Design
, vol.185
, pp. 33-49
-
-
Wisner, S.B.1
Adamson, R.B.2
-
7
-
-
0012910402
-
Investigation on the Post-Defect Deterioration of Nonbarrier BWR Failed Rods
-
West Palm Beach, FL, 17-21 April American Nuclear Society
-
Lin, K. F., Chung, C. S., Yeh, J. J., Chen, J. H., Chu, S. S., and Lin, L. F., "Investigation on the Post-Defect Deterioration of Nonbarrier BWR Failed Rods," Proceedings of the 1994 International Topical Meeting on Light Water Reactor Fuel Performance, West Palm Beach, FL, 17-21 April 1994, American Nuclear Society, pp. 377-390.
-
(1994)
Proceedings of the 1994 International Topical Meeting on Light Water Reactor Fuel Performance
, pp. 377-390
-
-
Lin, K.F.1
Chung, C.S.2
Yeh, J.J.3
Chen, J.H.4
Chu, S.S.5
Lin, L.F.6
-
8
-
-
0343253807
-
Effects of SPP Dissolution on Mechanical Properties of Zircaloy-2
-
Portland, 2-6 March American Nuclear Society
-
Mahmood, S. T., Edsinger, K. W., Farkas, D. M. and Adamson, R. B., "Effects of SPP Dissolution on Mechanical Properties of Zircaloy-2," Proceedings of the 1997 International Topical Meeting on Light Water Reactor Fuel Performance, Portland, 2-6 March 1994, American Nuclear Society, pp. 440-451.
-
(1994)
Proceedings of the 1997 International Topical Meeting on Light Water Reactor Fuel Performance
, pp. 440-451
-
-
Mahmood, S.T.1
Edsinger, K.W.2
Farkas, D.M.3
Adamson, R.B.4
-
9
-
-
0038554548
-
Secondary Defect Behavior in ABB BWR Fuel
-
West Palm Beach, FL, 17-21 April American Nuclear Society
-
Schrier, D., Lysell, G., Frenning, G., Rönnberg, G., and Jonsson, A., "Secondary Defect Behavior in ABB BWR Fuel," Proceedings of the 1994 International Topical Meeting on Light Water Reactor Fuel Performance, West Palm Beach, FL, 17-21 April 1994, American Nuclear Society, pp. 398-409.
-
(1994)
Proceedings of the 1994 International Topical Meeting on Light Water Reactor Fuel Performance
, pp. 398-409
-
-
Schrier, D.1
Lysell, G.2
Frenning, G.3
Rönnberg, G.4
Jonsson, A.5
-
10
-
-
0026223832
-
Delayed Hydride Cracking Behavior for Zircaloy-2 Tubing
-
Huang, F. H. and Mills, W. J., "Delayed Hydride Cracking Behavior for Zircaloy-2 Tubing," Metallurgical Transactions A, Vol. 22A, 1991, p. 2049.
-
(1991)
Metallurgical Transactions A
, vol.22 A
, pp. 2049
-
-
Huang, F.H.1
Mills, W.J.2
-
11
-
-
0342819168
-
-
this proceedings
-
Mahmood, S. T., Farkas, D. M., Adamson, R. B., and Etoh, Y., "Post-Irradiation Characterization of Ultra High Fluence Zircaloy-2 Plate," this proceedings.
-
Post-Irradiation Characterization of Ultra High Fluence Zircaloy-2 Plate
-
-
Mahmood, S.T.1
Farkas, D.M.2
Adamson, R.B.3
Etoh, Y.4
-
12
-
-
0030287689
-
The Influence of Temperature and Yield Strength on Delayed Hydride Cracking in Hydrided Zircaloy-2
-
E. R. Bradley and G. P. Sabol, Eds., American Society for Testing and Materials, Philadelphia
-
Efsing, P. and Pettersson, K., "The Influence of Temperature and Yield Strength on Delayed Hydride Cracking in Hydrided Zircaloy-2," Zirconium in the Nuclear Industry, ASTM STP 1295, E. R. Bradley and G. P. Sabol, Eds., American Society for Testing and Materials, Philadelphia, 1996, pp. 394-404.
-
(1996)
Zirconium in the Nuclear Industry, ASTM STP 1295
, pp. 394-404
-
-
Efsing, P.1
Pettersson, K.2
-
13
-
-
0342384301
-
Visual Examination and Light Microscopy
-
K. Mills, Ed., ASM, Metals Park, OH
-
Vander Voort, G. F., "Visual Examination and Light Microscopy," Metals Handbook Ninth Edition, Vol. 12 Fractography, K. Mills, Ed., ASM, Metals Park, OH, 1987, pp. 91-165.
-
(1987)
Metals Handbook Ninth Edition, Vol. 12 Fractography
, vol.12
, pp. 91-165
-
-
Vander Voort, G.F.1
-
14
-
-
0017915969
-
Impact Three-Point Bend Testing for Notched and Precracked Specimens
-
Server, W. L., "Impact Three-Point Bend Testing for Notched and Precracked Specimens," Journal of Testing and Evaluation, Vol. 6, No. 1, 1978, pp. 29-34.
-
(1978)
Journal of Testing and Evaluation
, vol.6
, Issue.1
, pp. 29-34
-
-
Server, W.L.1
-
15
-
-
0030290899
-
Fracture Toughness of Zircaloy Cladding Tubes
-
E. R. Bradley and G. P. Sabols, Eds., American Society for Testing and Materials, Philadelphia
-
Grigoriev, V., Josefsson, B., and Rosborg, B., "Fracture Toughness of Zircaloy Cladding Tubes," Zirconium in the Nuclear Industry, ASTM STP 1295, E. R. Bradley and G. P. Sabols, Eds., American Society for Testing and Materials, Philadelphia, 1996, pp. 431-447.
-
(1996)
Zirconium in the Nuclear Industry, ASTM STP 1295
, pp. 431-447
-
-
Grigoriev, V.1
Josefsson, B.2
Rosborg, B.3
-
16
-
-
0027872938
-
Brittle-Fracture Potential of Irradiated Zircaloy-2 Pressure Tubes
-
Huang, F. H., "Brittle-Fracture Potential of Irradiated Zircaloy-2 Pressure Tubes," Journal of Nuclear Materials, Vol. 207, 1993, pp. 103-115.
-
(1993)
Journal of Nuclear Materials
, vol.207
, pp. 103-115
-
-
Huang, F.H.1
-
18
-
-
85033892710
-
Variation of Zircaloy Fracture Toughness in Irradiation
-
J. H. Schemel and H. S. Rosenbaum, Eds., American Society for Testing and Materials, Philadelphia
-
Walker, T. J. and Kass, J. N., "Variation of Zircaloy Fracture Toughness in Irradiation," Zirconium in Nuclear Applications, ASTM STP 551, J. H. Schemel and H. S. Rosenbaum, Eds., American Society for Testing and Materials, Philadelphia, 1974, pp. 328-354.
-
(1974)
Zirconium in Nuclear Applications, ASTM STP 551
, pp. 328-354
-
-
Walker, T.J.1
Kass, J.N.2
-
19
-
-
0026383824
-
Effects of LiOH on Pretransition Zirconium Oxide Films
-
C. M. Euken and A. M. Garde, Eds., American Society for Testing and Materials, Philadelphia
-
Cox, B. and Wong, Y.-M., "Effects of LiOH on Pretransition Zirconium Oxide Films," Zirconium in the Nuclear Industry, ASTM STP 1132, C. M. Euken and A. M. Garde, Eds., American Society for Testing and Materials, Philadelphia, 1991, pp. 643-662.
-
(1991)
Zirconium in the Nuclear Industry, ASTM STP 1132
, pp. 643-662
-
-
Cox, B.1
Wong, Y.-M.2
-
20
-
-
0343253802
-
A Laboratory Method to Predict Hydriding Properties of Zirconium Alloys under Irradiation
-
L. F. P. Swam and C. M. Euken, Eds., American Society for Testing and Materials, Philadelphia
-
Johnson, A. B., Levy, I. S., Lanning, D. D., Gerber, F. S., and Trimble, D. J., "A Laboratory Method to Predict Hydriding Properties of Zirconium Alloys Under Irradiation," Zirconium in the Nuclear Industry: Eighth International Symposium, ASTM STP 1023, L. F. P. Swam and C. M. Euken, Eds., American Society for Testing and Materials, Philadelphia, 1989, pp. 153-164.
-
(1989)
Zirconium in the Nuclear Industry: Eighth International Symposium, ASTM STP 1023
, pp. 153-164
-
-
Johnson, A.B.1
Levy, I.S.2
Lanning, D.D.3
Gerber, F.S.4
Trimble, D.J.5
|