-
2
-
-
0343254681
-
LWR Fuel Performance and Material Development Activities for Extended Burnup in Russia
-
2-6 March
-
Solonin, M. I. et al., "LWR Fuel Performance and Material Development Activities for Extended Burnup in Russia," ANS Portland, 2-6 March 1997.
-
(1997)
ANS Portland
-
-
Solonin, M.I.1
-
3
-
-
0039934380
-
Effect of Microstructure on the Corrosion of Zr-2.5 Nb Alloy
-
Sept. Oregon
-
Urbanic, V. F. and Gilbert, R. W., "Effect of Microstructure on the Corrosion of Zr-2.5 Nb Alloy," AECL, IAEA Technical Committee Meeting, Sept. 1989, Oregon.
-
(1989)
AECL, IAEA Technical Committee Meeting
-
-
Urbanic, V.F.1
Gilbert, R.W.2
-
4
-
-
0343690354
-
A Metallographic Study of Annealing of Zr-1 Nb Nuclear Fuel Sheathing
-
Derek, A. D. and Northwood, G. A, "A Metallographic Study of Annealing of Zr-1 Nb Nuclear Fuel Sheathing," Microstructural Science, Vol. 17, 1989, p. 393.
-
(1989)
Microstructural Science
, vol.17
, pp. 393
-
-
Derek, A.D.1
Northwood, G.A.2
-
5
-
-
0030291013
-
Influence of Neutron Irradiation on Dislocation Structure and Phase Composition of Zr-Base Alloys
-
Shishov, V. N. et al., "Influence of Neutron Irradiation on Dislocation Structure and Phase Composition of Zr-Base Alloys," Zirconium in the Nuclear Industry (11th Volume), ASTM STP 1295, pp. 603-622.
-
Zirconium in the Nuclear Industry (11th Volume), ASTM STP 1295
, pp. 603-622
-
-
Shishov, V.N.1
-
6
-
-
0343254679
-
Update on the Development of Advanced Zirconium Alloys for PWR Fuel Rod Cladding
-
2-6 March
-
Mardon, J. P. et al., "Update on the Development of Advanced Zirconium Alloys for PWR Fuel Rod Cladding," ANS Portland, 2-6 March 1997, pp. 405-413.
-
(1997)
ANS Portland
, pp. 405-413
-
-
Mardon, J.P.1
-
7
-
-
0342820010
-
Influence des Traitements Thermiques sur les Propriétés des Tubes de Gainage en Alliages Zirconium-Niobium (1 et 2.5%Nb)-Etude Particulière du Comportement en Fluage Thermique Biaxé
-
15 Dec.
-
Golhen, J. F., "Influence des Traitements Thermiques sur les Propriétés des Tubes de Gainage en Alliages Zirconium-Niobium (1 et 2.5%Nb)-Etude Particulière du Comportement en Fluage Thermique Biaxé," Thèse CNAM Paris, 15 Dec. 1993, pp. 54-57.
-
(1993)
Thèse CNAM Paris
, pp. 54-57
-
-
Golhen, J.F.1
-
8
-
-
0343690356
-
-
ANS, West Palm Beach, April
-
Morel, M. et al., "Technique and Method for Upgrading Corrosion Performance Through Fragema Fuel Experience Feedback," ANS, West Palm Beach, April 1994, pp. 15-21.
-
(1994)
Technique and Method for Upgrading Corrosion Performance Through Fragema Fuel Experience Feedback
, pp. 15-21
-
-
Morel, M.1
-
9
-
-
0343690357
-
-
"French Patent," FR 2747397, 16 April 1996
-
Rebeyrolle, V., "French Patent," FR 2747397, 16 April 1996.
-
-
-
Rebeyrolle, V.1
-
10
-
-
85040301066
-
Creep of Zirconium Alloys in Nuclear Reactor
-
Franklin, D. G., Lucas, G. E., and Bement, A. L., "Creep of Zirconium Alloys in Nuclear Reactor," Creep of Zirconium Alloys in Nuclear Reactors, ASTM STP 815, 1983, p. 31.
-
(1983)
Creep of Zirconium Alloys in Nuclear Reactors, ASTM STP 815
, pp. 31
-
-
Franklin, D.G.1
Lucas, G.E.2
Bement, A.L.3
-
11
-
-
0032074007
-
Influence of Sulfur Content on the Thermal Creep of Zirconium Alloy Tubes at 400°C
-
Charquet, D., "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
-
12
-
-
0040109968
-
Optimization of PWR Behavior of Stress-Relieved Zircaloy-4 Cladding Tubes by Upgrading the Manufacturing and Inspection Process
-
Mardon, J. P., Charquet, D., and Senevat, J., "Optimization of PWR Behavior of Stress-Relieved Zircaloy-4 Cladding Tubes by Upgrading the Manufacturing and Inspection Process," Zirconium in the Nuclear Industry (10th Vol.), ASTM STP 1245, pp. 329-348.
-
Zirconium in the Nuclear Industry (10th Vol.), ASTM STP 1245
, pp. 329-348
-
-
Mardon, J.P.1
Charquet, D.2
Senevat, J.3
|