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The Application of Ductile Fracture Analysis to Predictions of Pressure Tube Failure
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2
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0025628455
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Leak-Before-Break in the Pressure Tubes of CANDU Reactors
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Moan, G. D., Coleman, C. E., Price, E. G., Rodgers, D. K., and Sagat, S., "Leak-Before-Break in the Pressure Tubes of CANDU Reactors," International Journal of Pressure Vessels and Piping, Vol. 43, 1990, pp. 1-21.
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8844286736
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Terminal Solubility and Partitioning of Hydrogen in α-Phase of Zirconium, Zircaloy-2 and Zircaloy-4
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Fabrication of Zr-2.5 Nb Pressure Tubes to Minimise the Harmful Effects of Trace Elements
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Theaker, J. R., Choubey, R., Moan, G. D., Aldridge, S. A., Davis, L., Graham, R. A., and Coleman, C. E., "Fabrication of Zr-2.5 Nb Pressure Tubes to Minimise the Harmful Effects of Trace Elements," Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245, A. M. Garde and E. R. Bradley, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1994, pp. 221-242.
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Aldridge, S.A.4
Davis, L.5
Graham, R.A.6
Coleman, C.E.7
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5
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5544303863
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Effect of Shot Peening and Post-Peening Heat Treatments on the Microstructure, the Residual Stress and Hardness, Corrosion and Deuterium Uptake Resistance of Zr-2.5 Nb Pressure Tube Material
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M. H. Aliabadi and C. A. Bzebbia, Eds., Computational Publications, Southampton
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Amouzouvi, K. F., Clegg, L. J., Styles, R. C., and Winegar, J. E., "Effect of Shot Peening and Post-Peening Heat Treatments on the Microstructure, the Residual Stress and Hardness, Corrosion and Deuterium Uptake Resistance of Zr-2.5 Nb Pressure Tube Material," Computer Methods and Experimental Measurements for Surface Treatment Effects, M. H. Aliabadi and C. A. Bzebbia, Eds., Computational Publications, Southampton, 1993.
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Computer Methods and Experimental Measurements for Surface Treatment Effects
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Amouzouvi, K.F.1
Clegg, L.J.2
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Winegar, J.E.4
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6
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5544239084
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Surface Modification of Zirconium Alloys by Laser Glazing
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The Reduction of Corrosion in Zr-2.5 Nb
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Ploc, R. A., Amouzouvi, K. F., and Turner, C. W., "The Reduction of Corrosion in Zr-2.5 Nb," Proceedings, 24th Annual Convention of the International Metallographic Society, Monterey, CA, July 1991, IMS, Columbus, OH.
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8
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e Colloque International sur la Corrosion et la Protection des Materiaux a Haute Temperature
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Ploc, R.A.1
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9
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5544322340
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Plating End Fittings to Reduce Hydrogen Ingress at Rolled Joints in CANDU Reactors
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White, A. J., Urbanic, V. F., Bahurmuz, A. A., Clendening, W. R., Joynes, R., McDougall, G. M., Skinner, B. C., and Venkatapathi, S., "Plating End Fittings to Reduce Hydrogen Ingress at Rolled Joints in CANDU Reactors," Proceedings, International Conference on Expanded and Rolled Joint Technology, Canadian Nuclear Society, Toronto, Ontario, Canada, September 1993, pp. G47-G55.
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International Conference on Expanded and Rolled Joint Technology
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White, A.J.1
Urbanic, V.F.2
Bahurmuz, A.A.3
Clendening, W.R.4
Joynes, R.5
McDougall, G.M.6
Skinner, B.C.7
Venkatapathi, S.8
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10
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5544244825
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Removal of Hydrogen from Rolled Joints in CANDU Reactors by Yttrium Sinks
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Proceedings, Canadian Nuclear Society, Toronto, Ontario, Canada, September
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Cann, C. D., Bahurmuz, A. A., Sexton, E. E., DeGregorio, R., Grant, I., Inglis, I., Murphy, E. V., and Natesan, M., "Removal of Hydrogen from Rolled Joints in CANDU Reactors by Yttrium Sinks," Proceedings, International Conference on Expanded and Rolled Joint Technology, Canadian Nuclear Society, Toronto, Ontario, Canada, September 1993, pp. H15-H24.
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International Conference on Expanded and Rolled Joint Technology
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Cann, C.D.1
Bahurmuz, A.A.2
Sexton, E.E.3
DeGregorio, R.4
Grant, I.5
Inglis, I.6
Murphy, E.V.7
Natesan, M.8
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11
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5544322341
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The Use of Hydrogen Getters for Prevention of Hydrogen Embrittlement in Zirconium-Alloy Fuel Cans
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E. F. Baroch, Ed., American Society for Testing and Materials, West Conshohocken, PA
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Spalthoff, W. and Wilhelm, H., "The Use of Hydrogen Getters for Prevention of Hydrogen Embrittlement in Zirconium-Alloy Fuel Cans," Zirconium in the Nuclear Industry, ASTM STP 458, E. F. Baroch, Ed., American Society for Testing and Materials, West Conshohocken, PA, 1969, pp. 338-344.
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Zirconium in the Nuclear Industry, ASTM STP 458
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Spalthoff, W.1
Wilhelm, H.2
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12
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0019897733
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Effect of Texture on Hydride Reorientation and Delayed Hydrogen Cracking in Cold-Worked Zr-2.5 Nb
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D. G. Franklin, Ed., American Society for Testing and Materials, West Conshohocken, PA
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Coleman, C. E., "Effect of Texture on Hydride Reorientation and Delayed Hydrogen Cracking in Cold-Worked Zr-2.5 Nb," Zirconium in the Nuclear Industry, ASTM STP 754, D. G. Franklin, Ed., American Society for Testing and Materials, West Conshohocken, PA, 1982, pp. 393-411.
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Zirconium in the Nuclear Industry, ASTM STP 754
, pp. 393-411
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Coleman, C.E.1
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13
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0008623214
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AECL-9524, Atomic Energy of Canada Ltd., Chalk River Laboratories, Chalk River, Ontario, Canada, December
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Coleman, C. E., Sagat, S., and Amouzouvi, K. F., "Control of Microstructure to Increase the Tolerance of Zirconium Alloys to Hydride Cracking," AECL-9524, Atomic Energy of Canada Ltd., Chalk River Laboratories, Chalk River, Ontario, Canada, December 1987.
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Control of Microstructure to Increase the Tolerance of Zirconium Alloys to Hydride Cracking
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Coleman, C.E.1
Sagat, S.2
Amouzouvi, K.F.3
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14
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0000915133
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The Effect of Fluence and Irradiation Temperature on Delayed Hydride Cracking in Zr-2.5Nb
-
A. M. Garde and E. R. Bradley, Eds., American Society for Testing and Materials, West Conshohocken, PA
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Sagat, S., Coleman, C. E., Griffiths, M., and Wilkins, B. J. S., "The Effect of Fluence and Irradiation Temperature on Delayed Hydride Cracking in Zr-2.5Nb," Zirconium in the Nuclear Industry, ASTM STP 1245, A. M. Garde and E. R. Bradley, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1994, pp. 35-61.
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Zirconium in the Nuclear Industry, ASTM STP 1245
, pp. 35-61
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Sagat, S.1
Coleman, C.E.2
Griffiths, M.3
Wilkins, B.J.S.4
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15
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84920638559
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this conference
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Chow, C. K., Coleman, C. E., Koike, M. H., Causey, A. R., Ells, C. E., Hosbons, R. R., Sagat, S., Urbanic, V. F., and Rodgers, D. K., "Properties of an Irradiated Heat-treated Zr-2.5Nb Pressure Tube Removed from the NPD Reactor," this conference.
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Properties of An Irradiated Heat-treated Zr-2.5Nb Pressure Tube Removed from the NPD Reactor
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-
Chow, C.K.1
Coleman, C.E.2
Koike, M.H.3
Causey, A.R.4
Ells, C.E.5
Hosbons, R.R.6
Sagat, S.7
Urbanic, V.F.8
Rodgers, D.K.9
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16
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0025725331
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Delayed Hydride Cracking Behavior for Zircaloy-2 Plate
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Mills, J. W. and Huang, F. H., "Delayed Hydride Cracking Behavior for Zircaloy-2 Plate," Engineering Fracture Mechanics, Vol. 39, 1991, pp. 241-257.
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Engineering Fracture Mechanics
, vol.39
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Mills, J.W.1
Huang, F.H.2
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17
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0026223832
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Delayed Hydride Cracking Behavior for Zircaloy-2 Tubing
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Huang, F. H. and Mills, W. J., "Delayed Hydride Cracking Behavior for Zircaloy-2 Tubing," Metallurgical Transactions, Vol. 22A, 1991, pp. 2049-2060.
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Metallurgical Transactions
, vol.22 A
, pp. 2049-2060
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Huang, F.H.1
Mills, W.J.2
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18
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0027656941
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Role of Microsegregation in Fracture of Cold-Worked Zr-2.5 Nb Pressure Tubes
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Aitchison, I. and Davies, P. H., "Role of Microsegregation in Fracture of Cold-Worked Zr-2.5 Nb Pressure Tubes," Journal of Nuclear Materials, Vol. 203, 1993, pp. 206-220.
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(1993)
Journal of Nuclear Materials
, vol.203
, pp. 206-220
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Aitchison, I.1
Davies, P.H.2
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19
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0343477678
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Correlation between Irradiated and Unirradiated Fracture Toughness of Zr-2.5 Nb Pressure Tubes
-
A. M. Garde and E. R. Bradley, Eds., American Society for Testing and Materials, West Conshohocken, PA
-
Davies, P. H., Hosbons, R. R., Griffiths, M., and Chow, C. K., "Correlation Between Irradiated and Unirradiated Fracture Toughness of Zr-2.5 Nb Pressure Tubes," Zirconium in the Nuclear Industry, ASTM STP 1245, A. M. Garde and E. R. Bradley, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1994, pp. 135-167.
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(1994)
Zirconium in the Nuclear Industry, ASTM STP 1245
, pp. 135-167
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-
Davies, P.H.1
Hosbons, R.R.2
Griffiths, M.3
Chow, C.K.4
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21
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0021615676
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Pressure Tube Development for CANDU Reactors
-
D. G. Franklin and R. B. Adamson, Eds., American Society for Testing and Materials, West Conshohocken, PA
-
Fleck, R. G., Price, E. G., and Cheadle, B. A., "Pressure Tube Development for CANDU Reactors," Zirconium in the Nuclear Industry, ASTM STP 824, D. G. Franklin and R. B. Adamson, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1984, pp. 88-105.
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(1984)
Zirconium in the Nuclear Industry, ASTM STP 824
, pp. 88-105
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-
Fleck, R.G.1
Price, E.G.2
Cheadle, B.A.3
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22
-
-
0024087799
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Mechanisms of Irradiation Growth of Alpha-Zirconium Alloys
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Journal of Nuclear Materials
, vol.159
, pp. 310-338
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Holt, R.A.1
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23
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84920638072
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this conference
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Choubey, R., Aldridge, S. A., Theaker, J. R., Cann, C. D., and Coleman, C. E., "Effects of Extrusion-Billet Pre-Heating on the Microstructure and Properties of Zr-2.5 Nb Pressure Tube Materials," this conference.
-
Effects of Extrusion-Billet Pre-Heating on the Microstructure and Properties of Zr-2.5 Nb Pressure Tube Materials
-
-
Choubey, R.1
Aldridge, S.A.2
Theaker, J.R.3
Cann, C.D.4
Coleman, C.E.5
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