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SEDL / STP / STP754-EB
This publication provides information on the performance of zirconium and zirconium alloy components in nuclear application. Nuclear physicists have discovered that some materials -- zirconium, for example, provide much better neutron economy than conventional materials such as stainless steels.
Table of Contents
Introduction
Franklin D.
Discussion
Summary
Franklin D.
A Review of Texture and Texture Formation in Zircaloy Tubing
Tenckhoff E.
Texture Control of Zircaloy Tubing During Tube Reduction
Fujita K., Kakuma T., Nagai N.
Texture Measurement Techniques for Zircaloy Cladding: A Round-Robin Study
Adamson R., Lewis J., Schoenberger G.
Application of Hydrostatic Extrusion to Fabrication of Zircaloy Tubing
Kakuma T., Kimpara M., Matsushita T., Nagai N.
Beta-Quenching of Zircaloy Cladding Tubes in Intermediate or Final Size—Methods to Improve Corrosion and Mechanical Properties
Andersson T., Vesterlund G.
New Intermetallic Compounds in Zircaloy-4
Charquet D., Grange J., Moulin L.
Long-Term Test Results of Promising New Zirconium Alloys
Castaldelli L., Fizzotti C., Lunde L.
Clad Failure Modeling
Ballinger R., Christensen R., Eilbert R., Oldberg S., Rumble E., Was G.
Chemical Aspects of Iodine-Induced Stress Corrosion Cracking of Zircaloys
Cubicciotti D., Jones R., Syrett B.
Effect of Zirconium Oxide on the Stress-Corrosion Susceptibility of Irradiated Zircaloy Cladding
Mattas R., Neimark L., Yaggee F.
Effects of Temperature and Pressure on the In-Reactor Creepdown of Zircaloy Fuel Cladding
Dodd C., Hobson D., Thoms K., van der Kaa T.
High-Strength, Creep-Resistant Excel Pressure Tubes
Causey A., Cheadle B., Fidleris V., Holt R., Urbanic V.
High-Temperature Irradiation Growth in Zircaloy
Adamson R., Fidleris V., Tucker R.
Zircaloy-4 Cladding Deformation During Power Reactor Irradiation
Franklin D.
Burst Criterion of Zircaloy Fuel Claddings in a Loss-of-Coolant Accident
Erbacher F., Neitzel H., Rosinger H., Schmidt H., Wiehr K.
An Experimental Study of the Deformation of Zircaloy PWR Fuel Rod Cladding Under Mainly Convective Cooling
Hindle E., Mann C.
Effect of Hydrogen on the Oxygen Embrittlement of Beta-Quenched Zircaloy-4 Fuel Cladding
Seiffert S.
Lifetime and Failure Strain Prediction for Material Subjected to Non-stationary Tensile Loading Conditions; Applications to Zircaloy-4
Boček M.
Flow Stress of Oxygen-Enriched Zircaloy-2 Between 1023 and 1873 K
Choubey R., Ells C., Holt R., Jonas J.
A Comparison of the High-Temperature Oxidation Behavior of Zircaloy-4 and Pure Zirconium
Campbell J., Pawel R.
Effect of Texture on Hydride Reorientation and Delayed Hydrogen Cracking in Cold-Worked Zr-2.5Nb
Coleman C.
Mechanism of Accelerated Corrosion in Zircaloy-4 Laser and Electron-Beam Welds
McDonald S., Sabol G.
Waterside Corrosion of Zircaloy-Clad Fuel Rods in a PWR Environment
Garzarolli F., Jorde D., Manzel R., Politano J., Smerd P.
Long-Term In-Reactor Corrosion and Hydriding of Zircaloy-2 Tubing
Hillner E.
Index
Committee: B10
Paper ID: STP754-EB
DOI: 10.1520/STP754-EB
ISBN-EB: 978-0-8031-4823-9
 ASTM International is a member of CrossRef.
0-8031-0754-4
978-0-8031-0754-0
STP754-EB
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