-
1
-
-
5544322420
-
-
Rapport EDF, HT M2/88-27
-
Baron, D., and Bouffioux, P., 1989, “Le Crayon Combustible des Reacteurs a Eau Pressurisee de Grande Puissance,” Rapport EDF, HT M2/88-27.
-
(1989)
Le Crayon Combustible Des Reacteurs a Eau Pressurisee De Grande Puissance
-
-
Baron, D.1
Bouffioux, P.2
-
2
-
-
0015382497
-
Effect of Neutron Irradiation on the Tensile Properties of Zircaloy-2 and Zircaloy-4
-
Higgy, R., and Hammad, F. H., 1972, “Effect of Neutron Irradiation on the Tensile Properties of Zircaloy-2 and Zircaloy-4,” J. Nucl. Mater., 44, pp. 215-277.
-
(1972)
J. Nucl. Mater
, vol.44
, pp. 215-277
-
-
Higgy, R.1
Hammad, F.H.2
-
3
-
-
13544270570
-
Irradiation Damage in Zirconium and its Alloys
-
Northwood, D. O., 1977, “Irradiation Damage in Zirconium and its Alloys,” AT. Energy Review, p. 154.
-
(1977)
AT. Energy Review
, pp. 154
-
-
Northwood, D.O.1
-
4
-
-
0019900582
-
Zircaloy-4 Cladding Deformation During Power Reactor Irradiation
-
Franklin, D. G., 1982, “Zircaloy-4 Cladding Deformation During Power Reactor Irradiation,” ASTM-STP 754, pp. 235-267.
-
(1982)
ASTM-STP
, vol.754
, pp. 235-267
-
-
Franklin, D.G.1
-
6
-
-
0021583939
-
-
6th International Symposium, ASTM-STP
-
Baty, D. L., Pavinick, W. A., Dietrich, M. R., Clevinger, G. S., and Papazo-glou, T. P., 1984, “Deformation Characteristics of Cold-Worked and Recrystallized Zircaloy-4 Cladding in Zirconium in the Nuclear Industry,” 6th International Symposium, ASTM-STP, 824, 306-339.
-
(1984)
Deformation Characteristics of Cold-Worked and Recrystallized Zircaloy-4 Cladding in Zirconium in the Nuclear Industry
, vol.824
, pp. 306-339
-
-
Baty, D.L.1
Pavinick, W.A.2
Dietrich, M.R.3
Clevinger, G.S.4
Papazo-Glou, T.P.5
-
7
-
-
85168662828
-
Deformation and Fracture Properties of Neutron-Irradiated Recrystallized Zircaloy-2 Cladding Under Uniaxial Tension, Zirconium in the Nuclear Industry, VlIth
-
Yasuda, T., Nakatsuka, M., and Yamashita, K., 1987, “Deformation and Fracture Properties of Neutron-Irradiated Recrystallized Zircaloy-2 Cladding Under Uniaxial Tension,” Zirconium in the Nuclear Industry, VlIth Int. ASTM 939, pp. 734-747.
-
(1987)
Int. ASTM
, vol.939
, pp. 734-747
-
-
Yasuda, T.1
Nakatsuka, M.2
Yamashita, K.3
-
8
-
-
5544315059
-
A Unified Model to Describe the Anisotropic Viscoplastic Behavior of Zircaloy-4 Cladding Tubes
-
Delobelle, P., Robinet, P., Bouffioux, P., Geyer, P., and Le Pichon, I., 1996, “A Unified Model to Describe the Anisotropic Viscoplastic Behavior of Zircaloy-4 Cladding Tubes,” Zirconium in the Nuclear Industry, 11th International Symposium, ASTM-STP 1295, pp. 373-393.
-
(1996)
Zirconium in the Nuclear Industry, 11Th International Symposium, ASTM-STP
, vol.1295
, pp. 373-393
-
-
Delobelle, P.1
Robinet, P.2
Bouffioux, P.3
Geyer, P.4
Le Pichon, I.5
-
9
-
-
0030283678
-
A Model to Describe the Anisotropic Viscoplastic Behavior of Zircaloy-4 Tubes
-
Delobelle, P., Robinet, P., Geyer, P., and Bouffioux, P., 1996, “A Model to Describe the Anisotropic Viscoplastic Behavior of Zircaloy-4 Tubes,” J. Nucl. Mater., 238, pp. 135-162.
-
(1996)
J. Nucl. Mater
, vol.238
, pp. 135-162
-
-
Delobelle, P.1
Robinet, P.2
Geyer, P.3
Bouffioux, P.4
-
10
-
-
0018458495
-
Relationship between Contractile Strain Ratio R and Texture in Zirconium Alloy Tubing
-
Van Swam, L. F., Knorr, D. B., Pelloux, R. M., and Shewbridge, J. F., 1979, “Relationship between Contractile Strain Ratio R and Texture in Zirconium Alloy Tubing,” Metall. Trans. A, 10, p. 483.
-
(1979)
Metall. Trans. A
, vol.10
, pp. 483
-
-
Van Swam, L.F.1
Knorr, D.B.2
Pelloux, R.M.3
Shewbridge, J.F.4
-
11
-
-
0343689470
-
An Experimental Method to Investigate the Anisotropic Viscoplastic Behavior of Zircaloy Cladding Tubes
-
Bouffioux, P., 1995, “An Experimental Method to Investigate the Anisotropic Viscoplastic Behavior of Zircaloy Cladding Tubes,” 11th International Symposium, ASTM-STP.
-
(1995)
11Th International Symposium, ASTM-STP
-
-
Bouffioux, P.1
-
12
-
-
13544250300
-
-
Report DER-EDF A4/94/012A. CEA, Framatome, and EDF Cooperative program, Proprietary data
-
Bouffioux, P., 1994, “Etude du Comportement en Plasticite des Tubes de Gainage en Zircaloy-4 Sous Sollicitations Biaxees,” Report DER-EDF A4/94/012A. CEA, Framatome, and EDF Cooperative program, 1995, Proprietary data.
-
(1994)
Etude Du Comportement En Plasticite Des Tubes De Gainage En Zircaloy-4 Sous Sollicitations Biaxees
-
-
Bouffioux, P.1
-
13
-
-
13544259336
-
Effect of Annealing Temperature on the Mechanical Properties of Zircaloy-4 Cladding
-
paper C3/5
-
Beauregard, R., Clevinger, G. S., and Murty, K. L., 1977, “Effect of Annealing Temperature on the Mechanical Properties of Zircaloy-4 Cladding,” Proceedings of the SMIRTIV, paper C3/5.
-
(1977)
Proceedings of the SMIRTIV
-
-
Beauregard, R.1
Clevinger, G.S.2
Murty, K.L.3
-
14
-
-
0342429089
-
-
Zirconium in the Nuclear Industry, VIIIth International Symposium, ASTM-STP
-
Murty, K. L., 1989, “Applications of Crystallographic Textures of Zirconium Alloys in Nuclear Industry,” Zirconium in the Nuclear Industry, VIIIth International Symposium, ASTM-STP 1023, p. 570.
-
(1989)
Applications of Crystallographic Textures of Zirconium Alloys in Nuclear Industry
, pp. 570
-
-
Murty, K.L.1
-
15
-
-
33751226117
-
Yielding and Dynamic Strain Aging Behavior of Zircaloy-4 Tube
-
Yi, J. K., Park, H. B., Park, G. S., and Lee, B. W., 1992, “Yielding and Dynamic Strain Aging Behavior of Zircaloy-4 Tube,” J. Nucl. Mater., 189, pp. 353.
-
(1992)
J. Nucl. Mater
, vol.189
, pp. 353
-
-
Yi, J.K.1
Park, H.B.2
Park, G.S.3
Lee, B.W.4
-
16
-
-
30244544391
-
-
SF2M, Journee d’Etudes Proprietes-Microstructures-Les Edit, Physique
-
Prioul, C., 1995, “Le Vieillissement Dynamique Dans les Alliages de Zirconium: Consequences Sur Les Proprietes Mecaniques,” SF2M, Journee d’Etudes Proprietes-Microstructures-Les Edit, Physique, pp. 25-34.
-
(1995)
“Le Vieillissement Dynamique Dans Les Alliages De Zirconium: Consequences Sur Les Proprietes Mecaniques
, pp. 25-34
-
-
Prioul, C.1
-
17
-
-
0442305054
-
-
SMIRT IV, San Francisco, Aug. 15-19, paper C3/4
-
Murty, K. L., Clevinger, G. S., and Papazoglou, T. P., 1977, “Thermal Creep of Zircaloy-4 Cladding,” SMIRT IV, San Francisco, Aug. 15-19, paper C3/4.
-
(1977)
Thermal Creep of Zircaloy-4 Cladding
-
-
Murty, K.L.1
Clevinger, G.S.2
Papazoglou, T.P.3
-
18
-
-
0023289853
-
Thermal Creep of Zircaloy-4 Cladding Under Internal Pressure
-
Matsuo, Y., 1987, “Thermal Creep of Zircaloy-4 Cladding Under Internal Pressure,” J. Nucl. Sci. Technol., 24, No. 2, pp. 111-119.
-
(1987)
J. Nucl. Sci. Technol
, vol.24
, Issue.2
, pp. 111-119
-
-
Matsuo, Y.1
-
19
-
-
13544251145
-
-
Lyashenko, V. S., Bykov, V. N., and Paulinov, L. B., 1959, Fiz. Met. Metalloved, 8, p. 362.
-
(1959)
Fiz. Met. Metalloved
, vol.8
, pp. 362
-
-
Lyashenko, V.S.1
Bykov, V.N.2
Paulinov, L.B.3
-
21
-
-
85040301066
-
Creep of Zirconium Alloys in Nuclear Reactors
-
Franklin, D. G., Lucas, G. E., and Bement, A. L., 1983, “Creep of Zirconium Alloys in Nuclear Reactors,” ASTM STP 815, p. 35.
-
(1983)
ASTM STP
, vol.815
, pp. 35
-
-
Franklin, D.G.1
Lucas, G.E.2
Bement, A.L.3
-
22
-
-
0030291865
-
-
11th International Symposium, ASTM-STP 1295
-
Huang, P., Mahmood, T., and Adamson, R., 1996, “Effects of Thermomechanical Processing on In-Reactor Corrosion and Post-Irradiation Mechanical Properties of Zircaloy-2,” 11th International Symposium, ASTM-STP 1295, pp. 726-755.
-
(1996)
Effects of Thermomechanical Processing on In-Reactor Corrosion and Post-Irradiation Mechanical Properties of Zircaloy-2
, pp. 726-755
-
-
Huang, P.1
Mahmood, T.2
Adamson, R.3
-
23
-
-
0006100968
-
-
Proceedings of Mecamat, International Seminar on Inelastic Behavior of Solids, Models and Utilization
-
Pilvin, P., 1988, “Identification Des Parametres de Modeles de Comportement,” Proceedings of Mecamat, International Seminar on Inelastic Behavior of Solids, Models and Utilization, pp. 155-164.
-
(1988)
“Identification Des Parametres De Modeles De Comportement
, pp. 155-164
-
-
Pilvin, P.1
-
24
-
-
5544252605
-
-
ASTM-STP 1295
-
Limback, M., and Anderson, T., 1996, “A Model for Analysis of the Effect of Final Annealing on the in-and out-of-Reactor Creep Behavior of Zircaloy Cladding,” ASTM-STP 1295, pp. 448-468.
-
(1996)
A Model for Analysis of the Effect of Final Annealing on the In-And Out-Of-Reactor Creep Behavior of Zircaloy Cladding
, pp. 448-468
-
-
Limback, M.1
Anderson, T.2
-
25
-
-
13544275320
-
Radiation Damage in Nuclear Fuel Materials
-
Matzke, H., 1993, “Radiation Damage in Nuclear Fuel Materials,” Solid State Phenomena, 30-31, pp. 355-366.
-
(1993)
Solid State Phenomena
, vol.30-31
, pp. 355-366
-
-
Matzke, H.1
|