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Zirconium in the Nuclear Industry Franklin DG Pages: 477       Published: 1982

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Table of Contents

Introduction
Franklin DG

Discussion


Summary
Franklin DG

A Review of Texture and Texture Formation in Zircaloy Tubing
Tenckhoff E

Texture Control of Zircaloy Tubing During Tube Reduction
Nagai N, Kakuma T, Fujita K

Texture Measurement Techniques for Zircaloy Cladding: A Round-Robin Study
Lewis JE, Schoenberger G, Adamson RB

Application of Hydrostatic Extrusion to Fabrication of Zircaloy Tubing
Nagai N, Kakuma T, Matsushita T, Kimpara M

Beta-Quenching of Zircaloy Cladding Tubes in Intermediate or Final SizeMethods to Improve Corrosion and Mechanical Properties
Andersson Th, Vesterlund G

New Intermetallic Compounds in Zircaloy-4
Grange JM, Charquet D, 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 RL, Syrett BC

Effect of Zirconium Oxide on the Stress-Corrosion Susceptibility of Irradiated Zircaloy Cladding
Mattas RF, Yaggee FL, Neimark LA

Effects of Temperature and Pressure on the In-Reactor Creepdown of Zircaloy Fuel Cladding
Hobson DO, Thoms KR, Dodd CV, van der Kaa T

High-Strength, Creep-Resistant Excel Pressure Tubes
Cheadle BA, Holt RA, Fidleris V, Causey AR, Urbanic VF

High-Temperature Irradiation Growth in Zircaloy
Adamson RB, Tucker RP, Fidleris V

Zircaloy-4 Cladding Deformation During Power Reactor Irradiation
Franklin DG

Burst Criterion of Zircaloy Fuel Claddings in a Loss-of-Coolant Accident
Erbacher FJ, Neitzel HJ, Rosinger H, Schmidt H, Wiehr K

An Experimental Study of the Deformation of Zircaloy PWR Fuel Rod Cladding Under Mainly Convective Cooling
Hindle ED, Mann CA

Effect of Hydrogen on the Oxygen Embrittlement of Beta-Quenched Zircaloy-4 Fuel Cladding
Seiffert SL

Lifetime and Failure Strain Prediction for Material Subjected to Non-stationary Tensile Loading Conditions; Applications to Zircaloy-4
Boek M

Flow Stress of Oxygen-Enriched Zircaloy-2 Between 1023 and 1873 K
Choubey R, Jonas JJ, Holt RA, Ells CE

A Comparison of the High-Temperature Oxidation Behavior of Zircaloy-4 and Pure Zirconium
Pawel RE, Campbell JJ

Effect of Texture on Hydride Reorientation and Delayed Hydrogen Cracking in Cold-Worked Zr-2.5Nb
Coleman CE

Mechanism of Accelerated Corrosion in Zircaloy-4 Laser and Electron-Beam Welds
McDonald SG, Sabol GP

Waterside Corrosion of Zircaloy-Clad Fuel Rods in a PWR Environment
Garzarolli F, Jorde D, Manzel R, Politano JR, Smerd PG

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

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STP754-EB