Zirconium in the Nuclear Industry: Eighth International Symposium, Issue 1023

Front Cover
Leo F. P. Van Swam, Craig M. Eucken
ASTM International, 1989 - Technology & Engineering - 780 pages
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Contents

A Laboratory Method to Predict Hydriding Properties of Zirconium Alloys Under
18
Oxidation and Deuterium Uptake of Zr2 5Nb Pressure Tubes in CANDUPHW
20
Evaluation of Zircaloy2 Pressure Tubes from NPDCHRISTOPHER E COLEMAN
35
Growth Fracture and Nondestructive Evaluation of Hydride Blisters in Zr2 5Nb
50
Effects of Hydride Morphology on Zr2 5Nb Fracture ToughnessANDREW c
66
Effects of Loading and Thermal Maneuvers on Delayed Hydride Cracking
89
Influence of Chemical Composition on Uniform Corrosion of ZirconiumBase Alloy
113
Correlation Between 400C Steam Corrosion Behavior Heat Treatment
128
Corrosion Performance of Zircaloy2 and Zircaloy4 PWR Fuel CladdingPETER
213
Development of a Cladding Alloy for High BurnupGEORGE p SABOL GERALD
227
Enhanced LowTemperature Oxidation of Zirconium Alloys Under
245
Internal Hydriding in Irradiated Defected Zircaloy Fuel RodsJOHN c CLAYTON
266
A Systematic Survey of the Factors Affecting Zircaloy Nodular CorrosionK EIZO
291
Corrosion Performance Ranking of Zircaloy2 for BWR ApplicationsPETER
315
Influence of Chemical Composition and Manufacturing Variables on Autoclave
334
Effects of Alloying Element Distribution on the Nodular Corrosion of Zircaloy
346

Influence of the Manufacturing Process on the Corrosion Resistance of Zircaloy4
141
Development of a Mechanistic Model to Assess the External Corrosion of
165
Lithium Uptake and the Accelerated Corrosion of Zirconium AlloysNATESAN
187
Microstructure and Corrosion Studies for Optimized PWR and BWR Zircaloy
202
Electron Microscopy Study of Oxide Films Formed on Zircaloy2 in Superheated
360
Heterogeneous Scale Growth During Steam Corrosion of Zircaloy4
374
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