Zirconium in the Nuclear Industry: Twelfth International Symposium
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Published By ASTM International

9780803124998

Latest Documents Most Cited Documents Contributed Authors Related Sources Related Keywords

Stress Distribution Measured by Raman Spectroscopy in Zirconia Films Formed by Oxidation of Zr-Based Alloys

Zirconium in the Nuclear Industry: Twelfth International Symposium ◽

10.1520/stp14332s ◽

2008 ◽

pp. 877-877-24 ◽

Cited By ~ 20

Author(s):

J Godlewski ◽

P Bouvier ◽

G Lucazeau ◽

L Fayette

Keyword(s):

Raman Spectroscopy ◽

Stress Distribution ◽

Zirconia Films

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Evaluation of Zircaloy-2 Cladding Corrosion Characteristics by Simulated BWR Corrosion Loop Test

Zirconium in the Nuclear Industry: Twelfth International Symposium ◽

10.1520/stp14325s ◽

2008 ◽

pp. 735-735-21

Author(s):

S Shimada ◽

K Asahi ◽

Y Nonaka ◽

M Sasaki ◽

T Kogai ◽

...

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Influence of Transition Elements Fe, Cr, and V on Long-Time Corrosion in PWRs

Zirconium in the Nuclear Industry: Twelfth International Symposium ◽

10.1520/stp14319s ◽

2008 ◽

pp. 609-609-14 ◽

Cited By ~ 4

Author(s):

Y Broy ◽

F Garzarolli ◽

A Seibold ◽

LF Van Swam

Keyword(s):

Transition Elements ◽

Long Time

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A New Fabrication Process for Zr-Lined Zircaloy-2 Tubing

Zirconium in the Nuclear Industry: Twelfth International Symposium ◽

10.1520/stp14311s ◽

2008 ◽

pp. 425-425-35 ◽

Cited By ~ 1

Author(s):

H Abe ◽

K Takeda ◽

A Uehira ◽

H Anada ◽

M Furugen

Keyword(s):

Fabrication Process

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Post-Irradiation Characterization of Ultra-High-Fluence Zircaloy-2 Plate

Zirconium in the Nuclear Industry: Twelfth International Symposium ◽

10.1520/stp14299s ◽

2008 ◽

pp. 139-139-31 ◽

Cited By ~ 11

Author(s):

ST Mahmood ◽

DM Farkas ◽

RB Adamson ◽

Y Etoh

Keyword(s):

High Fluence ◽

Post Irradiation

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Irradiation Creep and Growth Behavior, and Microstructural Evolution of Advanced Zr-Base Alloys

Zirconium in the Nuclear Industry: Twelfth International Symposium ◽

10.1520/stp14294s ◽

2008 ◽

pp. 51-51-23 ◽

Cited By ~ 13

Author(s):

D Gilbon ◽

A Soniak ◽

S Doriot ◽

J-P Mardon

Keyword(s):

Microstructural Evolution ◽

Growth Behavior ◽

Irradiation Creep

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Subject Index

Zirconium in the Nuclear Industry: Twelfth International Symposium ◽

10.1520/stp40004s ◽

2008 ◽

pp. 949-949-5

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Multi-Scale Characterization of the Metal-Oxide Interface of Zirconium Alloys

Zirconium in the Nuclear Industry: Twelfth International Symposium ◽

10.1520/stp14334s ◽

2008 ◽

pp. 918-918-27 ◽

Cited By ~ 34

Author(s):

P Bossis ◽

G Lelièvre ◽

P Barberis ◽

X Iltis ◽

F Lefebvre

Keyword(s):

Metal Oxide ◽

Zirconium Alloys ◽

Oxide Interface ◽

Multi Scale ◽

Scale Characterization

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Hydrogen Transport in the Oxide and Hydrogen Pickup by the Metal During Out- and In-Reactor Corrosion of Zr-2.5Nb Pressure Tube Material

Zirconium in the Nuclear Industry: Twelfth International Symposium ◽

10.1520/stp14331s ◽

2008 ◽

pp. 853-853-24 ◽

Cited By ~ 6

Author(s):

N Ramasubramanian ◽

V Perovic ◽

M Leger

Keyword(s):

Pressure Tube ◽

Hydrogen Transport ◽

Tube Material ◽

Hydrogen Pickup

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Contribution to the Understanding of the Effect of the Water Chemistry on the Oxidation Kinetics of Zircaloy-4 Cladding

Zirconium in the Nuclear Industry: Twelfth International Symposium ◽

10.1520/stp14328s ◽

2008 ◽

pp. 793-793-18 ◽

Cited By ~ 17

Author(s):

D Pe^cheur ◽

J Godlewski ◽

J Peybernès ◽

L Fayette ◽

M Noé ◽

...

Keyword(s):

Water Chemistry ◽

Oxidation Kinetics ◽

Kinetics Of

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Zirconium in the Nuclear Industry: Twelfth International SymposiumLatest Publications

TOTAL DOCUMENTS

H-INDEX

Published By ASTM International

Stress Distribution Measured by Raman Spectroscopy in Zirconia Films Formed by Oxidation of Zr-Based Alloys

Evaluation of Zircaloy-2 Cladding Corrosion Characteristics by Simulated BWR Corrosion Loop Test

Influence of Transition Elements Fe, Cr, and V on Long-Time Corrosion in PWRs

A New Fabrication Process for Zr-Lined Zircaloy-2 Tubing

Post-Irradiation Characterization of Ultra-High-Fluence Zircaloy-2 Plate

Irradiation Creep and Growth Behavior, and Microstructural Evolution of Advanced Zr-Base Alloys

Subject Index

Multi-Scale Characterization of the Metal-Oxide Interface of Zirconium Alloys

Hydrogen Transport in the Oxide and Hydrogen Pickup by the Metal During Out- and In-Reactor Corrosion of Zr-2.5Nb Pressure Tube Material

Contribution to the Understanding of the Effect of the Water Chemistry on the Oxidation Kinetics of Zircaloy-4 Cladding

Zirconium in the Nuclear Industry: Twelfth International Symposium
Latest Publications