Irradiation Growth of Zircaloy

Zirconium in the Nuclear Industry ◽

10.1520/stp35579s ◽

2009 ◽

pp. 326-326-18 ◽

Cited By ~ 8

Author(s):

RB Adamson

Keyword(s):

Irradiation Growth

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Thermal Analysis and Irradiation Growth of Coated Zirconium Alloy Cladding Specimens in HFIR

10.2172/1649120 ◽

2020 ◽

Author(s):

Patrick Champlin ◽

Christian Petrie ◽

Annabelle Le Coq ◽

Kurt Smith ◽

Kory Linton

Keyword(s):

Thermal Analysis ◽

Zirconium Alloy ◽

Irradiation Growth

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Finite element simulation of gap opening between cladding tube and spacer grid in a fuel rod assembly using crystallographic models of irradiation growth and creep

Nuclear Engineering and Design ◽

10.1016/j.nucengdes.2017.02.029 ◽

2017 ◽

Vol 315 ◽

pp. 155-169 ◽

Cited By ~ 8

Author(s):

Anirban Patra ◽

Carlos N. Tomé

Keyword(s):

Finite Element ◽

Finite Element Simulation ◽

Spacer Grid ◽

Fuel Rod ◽

Irradiation Growth ◽

Element Simulation ◽

Gap Opening

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IRRADIATION GROWTH OF EBR-II FUEL PINS.

10.2172/4688048 ◽

1971 ◽

Author(s):

E.F. Sturcken ◽

G.G. Wicks

Keyword(s):

Irradiation Growth

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Interfacing VPSC with finite element codes. Demonstration of irradiation growth simulation in a cladding tube

10.2172/1244382 ◽

2016 ◽

Author(s):

Anirban Patra ◽

Carlos Tome

Keyword(s):

Finite Element ◽

Growth Simulation ◽

Irradiation Growth

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Irradiation Growth of Annealed Zircaloy-2

Zirconium in the Nuclear Industry ◽

10.1520/stp34481s ◽

2008 ◽

pp. 376-376-18 ◽

Cited By ~ 1

Author(s):

J Williams ◽

EC Darby ◽

DCC Minty

Keyword(s):

Irradiation Growth

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Irradiation Growth in Zirconium and Its Alloys

Effects of Radiation on Structural Materials ◽

10.1520/stp38158s ◽

2009 ◽

pp. 62-62-15 ◽

Cited By ~ 3

Author(s):

DO Northwood

Keyword(s):

Irradiation Growth

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Understanding Irradiation Growth through Atomistic Simulations: Defect Diffusion and Clustering in α-Zirconium and the Influence of Alloying Elements

Zirconium in the Nuclear Industry: 18th International Symposium ◽

10.1520/stp159720160093 ◽

2018 ◽

pp. 645-675

Author(s):

Mikael Christensen ◽

Walter Wolf ◽

Clive Freeman ◽

Erich Wimmer ◽

Ronald B. Adamson ◽

...

Keyword(s):

Alloying Elements ◽

Atomistic Simulations ◽

Defect Diffusion ◽

Irradiation Growth

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Ultra Low Tin Quaternary Alloys PWR Performance—Impact of Tin Content on Corrosion Resistance, Irradiation Growth, and Mechanical Properties

Zirconium in the Nuclear Industry: 16th International Symposium ◽

10.1520/stp152920120032 ◽

2011 ◽

pp. 801-826 ◽

Cited By ~ 4

Author(s):

V. Chabretou ◽

P. B. Hoffmann ◽

S. Trapp-Pritsching ◽

G. Garner ◽

P. Barberis ◽

...

Keyword(s):

Mechanical Properties ◽

Corrosion Resistance ◽

Quaternary Alloys ◽

Performance Impact ◽

Irradiation Growth ◽

Tin Content

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Accelerated Irradiation Growth of Zirconium Alloys

Zirconium in the Nuclear Industry: Eighth International Symposium ◽

10.1520/stp18892s ◽

2008 ◽

pp. 658-658-20 ◽

Cited By ~ 13

Author(s):

M Griffiths ◽

RW Gilbert ◽

V Fidleris

Keyword(s):

Zirconium Alloys ◽

Irradiation Growth

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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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