-
1
-
-
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
-
2
-
-
84920630185
-
Summary of experimental results on in reactor creep and irradiation growth of zirconium alloys
-
Fidleris, V., "Summary of Experimental Results on In Reactor Creep and Irradiation Growth of Zirconium Alloys," Atomic Energy Review, Vol. 13, 1975, pp. 50-80.
-
(1975)
Atomic Energy Review
, vol.13
, pp. 50-80
-
-
Fidleris, V.1
-
3
-
-
85168710739
-
In-reactor deformation of Zr-2.5wt% Nb pressure tubes
-
F. A. Garner, C. H. Henager, Jr., and N. Igata, Eds., American Society for Testing and Materials, Philadelphia
-
Causey, A. R., Fidleris, V., MacEwen, S. R., and Schulte, C. W., "In-Reactor Deformation of Zr-2.5wt% Nb Pressure Tubes," Influence of Radiation on Material Properties: 13th International Symposium (Part II), ASTM STP 956, F. A. Garner, C. H. Henager, Jr., and N. Igata, Eds., American Society for Testing and Materials, Philadelphia, 1987, pp. 54-68.
-
(1987)
Influence of Radiation on Material Properties: 13th International Symposium (Part II), ASTM STP
, vol.956
, pp. 54-68
-
-
Causey, A.R.1
Fidleris, V.2
MacEwen, S.R.3
Schulte, C.W.4
-
4
-
-
0030287691
-
Modeling in-reactor deformation of Zr-2.5Nb pressure tubes in CANDU power reactors
-
E. R. Bradley and G. P. Sabol, Eds., American Society for Testing and Materials
-
Christodoulou, N., Causey, A. R., Holt, R. A., Tomé, C. N., Badie, N., Klassen, R. J., Sauvé, R., and Woo, C. H., "Modeling In-Reactor Deformation of Zr-2.5Nb Pressure Tubes in CANDU Power Reactors," Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295, E. R. Bradley and G. P. Sabol, Eds., American Society for Testing and Materials, 1996, pp. 518-537.
-
(1996)
Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP
, vol.1295
, pp. 518-537
-
-
Christodoulou, N.1
Causey, A.R.2
Holt, R.A.3
Tomé, C.N.4
Badie, N.5
Klassen, R.J.6
Sauvé, R.7
Woo, C.H.8
-
5
-
-
0024087935
-
Implications of zircaloy creep and growth to light water reactor performance
-
Franklin, D. G. and Adamson, R. B., "Implications of Zircaloy Creep and Growth to Light Water Reactor Performance," Journal of Nuclear Materials, Vol. 159, 1988, pp. 12-21.
-
(1988)
Journal of Nuclear Materials
, vol.159
, pp. 12-21
-
-
Franklin, D.G.1
Adamson, R.B.2
-
6
-
-
0024087716
-
The irradiation creep and growth phenomena
-
Fidleris, V., "The Irradiation Creep and Growth Phenomena." Journal of Nuclear Materials, Vol. 159, 1988, pp. 22-42.
-
(1988)
Journal of Nuclear Materials
, vol.159
, pp. 22-42
-
-
Fidleris, V.1
-
7
-
-
0033907093
-
Irradiation-enhanced deformation of Zr-2.5Nb tubes at high neutron fluences
-
G. P. Sabol and G. D. Moan, Eds., American Society for Testing and Materials, West Conshohocken, PA
-
Causey, A. R., Holt, R. A., Christodoulou, N., and Ho, E. T. C., "Irradiation-Enhanced Deformation of Zr-2.5Nb Tubes at High Neutron Fluences," Zirconium in the Nuclear Industry: Twelfth International Symposium, ASTM STP 1354, G. P. Sabol and G. D. Moan, Eds., American Society for Testing and Materials, West Conshohocken, PA, 2000, pp. 74-85.
-
(2000)
Zirconium in the Nuclear Industry: Twelfth International Symposium, ASTM STP
, vol.1354
, pp. 74-85
-
-
Causey, A.R.1
Holt, R.A.2
Christodoulou, N.3
Ho, E.T.C.4
-
8
-
-
0033906314
-
Irradiation creep and growth behavior, and microstructural evolution of advanced Zr-base alloys
-
G. P. Sabol and G. D. Moan, Eds., American Society for Testing and Materials, West Conshohocken, PA
-
Gilbon, D., Soniak, A., Doriot, S., and Mardon, J.-P, "Irradiation Creep and Growth Behavior, and Microstructural Evolution of Advanced Zr-Base Alloys," Zirconium in the Nuclear Industry: Twelfth International Symposium, ASTM STP 1354, G. P. Sabol and G. D. Moan, Eds., American Society for Testing and Materials, West Conshohocken, PA, 2000, pp. 51-73.
-
(2000)
Zirconium in the Nuclear Industry: Twelfth International Symposium, ASTM STP
, vol.1354
, pp. 51-73
-
-
Gilbon, D.1
Soniak, A.2
Doriot, S.3
Mardon, J.-P.4
-
9
-
-
0040109968
-
Optimization of PWR behavior of stress-relieved zircaloy-4 cladding tubes by upgrading the manufacturing and inspection process
-
A. M. Garde and E. R. Bradley. Eds., American Society for Testing and Materials, Philadelphia
-
Mardon, J.-P., et al., "Optimization of PWR Behavior of Stress-relieved Zircaloy-4 Cladding Tubes by Upgrading the Manufacturing and Inspection Process," 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, Philadelphia, 1994, pp. 329-348.
-
(1994)
Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP
, vol.1245
, pp. 329-348
-
-
Mardon, J.-P.1
-
10
-
-
0343689417
-
FRAMATOME and PCF recent operating experience and advanced features to increase performance and reliability
-
2-6 March 1997
-
Ravier, G., et al., "FRAMATOME and PCF Recent Operating Experience and Advanced Features to Increase Performance and Reliability," ANS Portland, 2-6 March 1997, pp. 31-38.
-
ANS Portland
, pp. 31-38
-
-
Ravier, G.1
-
11
-
-
0343254679
-
Update on the development of advanced zirconium alloys for PWR fuel rod claddings
-
2-6 March
-
Mardon, J.-P., Garner, G., Beslu, P., and Charquet, D., "Update on the Development of Advanced Zirconium Alloys for PWR Fuel Rod Claddings," ANS Portland, 2-6 March 1997, pp. 405-412.
-
(1997)
ANS Portland
, pp. 405-412
-
-
Mardon, J.-P.1
Garner, G.2
Beslu, P.3
Charquet, D.4
-
12
-
-
0033892352
-
Influence of composition and fabrication process on out-Of-pile and in-pile properties of M5 alloy
-
G. P. Sabol and G. D. Moan, Eds., American Society for Testing and Materials, West Conshohocken, PA
-
Mardon, J.-P., Charquet, D., and Senevat, J., "Influence of Composition and Fabrication Process on Out-of-Pile and In-Pile Properties of M5 Alloy," Zirconium in the Nuclear Industry: Twelfth International Symposium, ASTM STP 1354, G. P. Sabol and G. D. Moan, Eds., American Society for Testing and Materials, West Conshohocken, PA, 2000, pp. 505-524.
-
(2000)
Zirconium in the Nuclear Industry: Twelfth International Symposium, ASTM STP
, vol.1354
, pp. 505-524
-
-
Mardon, J.-P.1
Charquet, D.2
Senevat, J.3
-
13
-
-
0032074007
-
Influence of sulfur content on the thermal creep of zirconium alloy tubes at 400°C
-
Charquet, D., Senevat, J., and Mardon, J.-P, "Influence of Sulfur Content on the Thermal Creep of Zirconium Alloy Tubes at 400°C," Journal of Nuclear Materials, Vol. 255, 1998, pp. 78-82.
-
(1998)
Journal of Nuclear Materials
, vol.255
, pp. 78-82
-
-
Charquet, D.1
Senevat, J.2
Mardon, J.-P.3
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