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

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Corrosion of Zircaloy in the Presence of LiOH

Zirconium in the Nuclear Industry: Ninth International Symposium ◽

10.1520/stp25529s ◽

2009 ◽

pp. 595-595-17 ◽

Author(s):

RA Perkins ◽

RA Busch

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Effect of Alloying Elements on Uniform Corrosion Resistance of Zirconium-based Alloys in 360°C Water and 400°C Steam

Zirconium in the Nuclear Industry: Ninth International Symposium ◽

10.1520/stp25518s ◽

2009 ◽

pp. 368-368-24 ◽

Author(s):

M Harada ◽

M Kimpara ◽

K Abe

Keyword(s):

Corrosion Resistance ◽

Alloying Elements ◽

Uniform Corrosion ◽

Effect Of Alloying

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Investigation of Nodular Corrosion Mechanism for Zircaloy Products

Zirconium in the Nuclear Industry: Ninth International Symposium ◽

10.1520/stp25515s ◽

2009 ◽

pp. 319-319-26

Author(s):

CT Wang ◽

CM Eucken ◽

RA Graham

Keyword(s):

Corrosion Mechanism

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Discussion

Zirconium in the Nuclear Industry: Ninth International Symposium ◽

10.1520/stp25514s ◽

2009 ◽

pp. 316-316-3

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Influence of Alloy Composition and Processing on the Nodular Corrosion Resistance of Zircaloy-2

Zirconium in the Nuclear Industry: Ninth International Symposium ◽

10.1520/stp25513s ◽

2009 ◽

pp. 304-304-12 ◽

Author(s):

ER Bradley ◽

JH Schemel ◽

A-L Nystöm

Keyword(s):

Corrosion Resistance ◽

Alloy Composition

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Fracture Toughness Evaluation of Heat-Treated Zr-2.5Nb Pressure Tubes

Zirconium in the Nuclear Industry: Ninth International Symposium ◽

10.1520/stp25501s ◽

2009 ◽

pp. 99-99-19 ◽

Author(s):

T Asada ◽

H Kimoto ◽

N Chiba ◽

Y Kasai

Keyword(s):

Fracture Toughness ◽

Heat Treated ◽

Pressure Tubes ◽

Toughness Evaluation ◽

Fracture Toughness Evaluation

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Deformability of Zirconium-Lined Cladding Tube in Cold Pilgering

Zirconium in the Nuclear Industry: Ninth International Symposium ◽

10.1520/stp25497s ◽

2009 ◽

pp. 35-35-13

Author(s):

H Abe ◽

H Tarui ◽

T Kobayashi ◽

M Honji ◽

T Konishi

Keyword(s):

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Characteristics of Autoclave and In-Reactor Nodular Corrosion of Zircaloys

Zirconium in the Nuclear Industry: Ninth International Symposium ◽

10.1520/stp25535s ◽

2009 ◽

pp. 683-683-35 ◽

Author(s):

YH Jeong ◽

KS Rheem ◽

HM Chung

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Effects Of LiOH on Pretransition Zirconium Oxide Films

Zirconium in the Nuclear Industry: Ninth International Symposium ◽

10.1520/stp25533s ◽

2009 ◽

pp. 643-643-20 ◽

Author(s):

B Cox ◽

Y-M Wong

Keyword(s):

Zirconium Oxide ◽

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Effect of Tensile Deformation on Crystallographic Texture in Zircaloy Sheet

Zirconium in the Nuclear Industry: Ninth International Symposium ◽

10.1520/stp25503s ◽

2009 ◽

pp. 119-119-21 ◽

Author(s):

ST Mahmood ◽

KL Murty

Keyword(s):

Crystallographic Texture ◽

Tensile Deformation

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