Zirconium in the Nuclear Industry
Latest Publications

TOTAL DOCUMENTS

36

(FIVE YEARS 0)

H-INDEX

5

(FIVE YEARS 0)

Published By ASTM International

9780803106017

Latest Documents Most Cited Documents Contributed Authors Related Sources Related Keywords

A Comparison of Experimental Cladding Microstructure Resulting from Uranium Oxide-Zircaloy Interaction with a Diffusional Assessment of Oxygen Transport for a Coupled Two-Media Problem

Zirconium in the Nuclear Industry ◽

10.1520/stp36690s ◽

2009 ◽

pp. 354-354-16

Author(s):

AW Cronenberg ◽

MS El-Genk

Keyword(s):

Oxygen Transport ◽

Uranium Oxide

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Out-of-Pile Testing of Iodine Stress Corrosion Cracking in Zircaloy Tubing in Relation to the Pellet-Cladding Interaction Phenomenon

Zirconium in the Nuclear Industry ◽

10.1520/stp36684s ◽

2009 ◽

pp. 244-244-17 ◽

Cited By ~ 10

Author(s):

M Peehs ◽

H Stehle ◽

E Steinberg

Keyword(s):

Stress Corrosion ◽

Stress Corrosion Cracking ◽

Corrosion Cracking ◽

Pile Testing ◽

Interaction Phenomenon

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Irradiation Growth in Cold-Worked Zircaloy-2

Zirconium in the Nuclear Industry ◽

10.1520/stp36682s ◽

2009 ◽

pp. 213-213-14 ◽

Cited By ~ 3

Author(s):

RA Murgatroyd ◽

A Rogerson

Keyword(s):

Irradiation Growth ◽

Cold Worked

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A Survey of the Chemical Environments for Activity in the Embrittlement of Zircaloy-2

Zirconium in the Nuclear Industry ◽

10.1520/stp36677s ◽

2009 ◽

pp. 145-145-10

Author(s):

WT Grubb ◽

MH Morgan

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Performance of Irradiated Copper and Zirconium Barrier-Modified Zircaloy Cladding Under Simulated Pellet-Cladding Interaction Conditions

Zirconium in the Nuclear Industry ◽

10.1520/stp36676s ◽

2009 ◽

pp. 122-122-23 ◽

Cited By ~ 2

Author(s):

DS Tomalin ◽

RB Adamson ◽

RP Gangloff>

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Localized Ductility Method for Evaluating Zircaloy-2 Cladding

Zirconium in the Nuclear Industry ◽

10.1520/stp36673s ◽

2009 ◽

pp. 72-72-16 ◽

Cited By ~ 1

Author(s):

LF Coffin

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Effect of Material and Environmental Variables on Localized Corrosion of Zirconium Alloys

Zirconium in the Nuclear Industry ◽

10.1520/stp36671s ◽

2009 ◽

pp. 40-40-20 ◽

Cited By ~ 3

Author(s):

L Lunde ◽

K Videm

Keyword(s):

Environmental Variables ◽

Zirconium Alloys ◽

Localized Corrosion

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A Proposed Criterion for the Oxygen Embrittlement of Zircaloy-4 Fuel Cladding

Zirconium in the Nuclear Industry ◽

10.1520/stp36697s ◽

2009 ◽

pp. 479-479-18 ◽

Cited By ~ 6

Author(s):

A Sawatzky

Keyword(s):

Fuel Cladding

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Effect of β-Phase Heat Treatment on the Subsequent α-Phase Ballooning Behavior of Zircaloy-4 Fuel Sheaths

Zirconium in the Nuclear Industry ◽

10.1520/stp36695s ◽

2009 ◽

pp. 447-447-18 ◽

Cited By ~ 1

Author(s):

CEL Hunt ◽

WG Newell

Keyword(s):

Heat Treatment ◽

Β Phase ◽

Α Phase

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A Stress Corrosion Cracking Model for Pellet-Cladding Interaction Failures in Light-Water Reactor Fuel Rods

Zirconium in the Nuclear Industry ◽

10.1520/stp36686s ◽

2009 ◽

pp. 285-285-21 ◽

Cited By ~ 6

Author(s):

JTA Roberts ◽

RL Jones ◽

D Cubicciotti ◽

AK Miller ◽

HF Wachob ◽

...

Keyword(s):

Stress Corrosion ◽

Stress Corrosion Cracking ◽

Corrosion Cracking ◽

Reactor Fuel ◽

Light Water Reactor ◽

Fuel Rods ◽

Light Water ◽

Water Reactor

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