Zirconium in the nuclear industry [electronic resource] : fourteenth international symposium /
Peter Rudling and Bruce Kammenzind, editors.
West Conshohocken, Pa. : ASTM, 2006.
x, 928 p. : ill. ; 24 cm.
0803134932, 9780803134935
More Details
series title
West Conshohocken, Pa. : ASTM, 2006.
Licensed for access by U. of T. users.
general note
"Papers presented at the 14th International Symposium on Zirconium in the Nuclear Industry held in Stockholm, Sweden, June 13 through 17, 2004"--P. ix.
catalogue key
Includes bibliographical references and indexes.
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Table of Contents
ZIRLO - an alloy development successp. 3
Review of deformation mechanisms, texture, and mechanical anisotropy in zirconium and zirconium base alloysp. 25
Plastic deformation of irradiated zirconium alloys : TEM investigations and micro-mechanical modelingp. 53
Study of Nb and Fe precipitation in [alpha]-phase temperature range (400 to 550[degree]C) in Zr-Nb-(Fe-Sn) alloysp. 81
On secondary [beta]-Nb phase precipitation within primary [alpha]-Zr Phase in Zr-Nb alloys during tensile deformationp. 102
Microstructure and phase control in Zr-Fe-Cr-Ni alloys : thermodynamic and kinetic aspectsp. 129
Modeling of the simultaneous evolution of vacancy and interstital dislocation loops in HCP metals under irradiationp. 157
Microstructural stability of M5 alloy irradiated up to high neutron fluencesp. 175
Microstructure and growth mechanism of oxide layers formed on Zr alloys studied with micro-beam synchrotron radiationp. 205
Simulation of cold pilgering process by a generalize plane strain FEMp. 233
Temperature and strain rate effects on Zr-1%Nb alloy deformationp. 248
Phase composition structure, and plastic deformation localization in Zar1%NB alloysp. 264
The effect of beta-quenching in final dimension on the irradiation growth of tubes and channelsp. 276
Destruction of crystallographic texture in zirconium alloy tubesp. 305
Improved ZIRLO cladding performance through chemistry and process modificationsp. 330
Role of iron for hydrogen absorption mechanism in zirconium alloysp. 349
In-situ studies of the oxide film properties on BWR fuel cladding materialsp. 367
The correlation between microstructures and in-BWR corrosion behavior of highly irradiated Zr-based alloysp. 386
Effect of alloying elements and impurities on in-BWR corrosion of zirconium alloysp. 404
In-core tests of effects of BWR water chemistry impurities on zircaloy corrosionp. 418
Shadow corrosion mechanism of zircaloyp. 445
TEM examinations of the metal-oxide interface of zirconium based alloys irradiated in a pressurized water reactorp. 467
Comparison of the high burn-up corrosion on M5 and low tin zircaloy-4p. 494
The effect of duplex cladding outer component tin content on corrosion, hydrogen pick-up, and hydride distribution at very high burnupp. 526
Predicting oxidation and deuterium ingress for Zr-2.5Nb CANDU pressure tubesp. 547
Inhibitors for reducing hydrogen ingress during corrosion of zirconium alloysp. 563
Identification of crystalline behavior on macroscopic response and local strain field analysis : application to alpha zirconium alloysp. 585
Ductility of zircaloy-4 fuel cladding and guide tubes at high fluencesp. 604
Thermal creep of irradiated zircaloy claddingp. 632
Use of the irradiation-thermal creep model of Zr-1% Nb alloy cladding tubes to describe dimensional changes of VVER fuel rodsp. 651
Influence of structure - phase state of Nb containing Zr alloys on irradiation-induced growthp. 666
Damage dependence of irradiation deformation of Zr-2.5Nb pressure tubesp. 686
Delayed hydrogen cracking velocity and J-integral measurements on irradiated BWR claddingp. 711
Overload fracture of flaw tip hydrides in Zr-2.5Nb pressure tubesp. 729
Effect of irradiation on the fracture properties of Zr-2.5Nb pressure tubes at the end of design lifep. 759
Effect of fabrication variables on irradiation response of crack growth resistance of Zr-2.5Nbp. 783
Fretting-wear behavior of zircaloy-4, OPTIN, and ZIRLO fuel rods and grid supports under various autoclave and hydraulic loop endurance test conditionsp. 802
Failure of hydrided zircaloy-4 under equal-biaxial and plane-strain tensile deformationp. 833
Mechanical properties of zircaloy-4 PWR fuel cladding with burnup 54-64MWd/kgU and implications for RIA behaviorp. 851
The effect of liner component iron content on cladding corrosion, hydriding, and PCI resistancep. 873
Influence of long service exposures on the thermal-mechanical behavior of Zy-4 and M5 alloys in LOCA conditionsp. 896
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