Spallation of oxide from stainless steel AGR nuclear fuel cladding: mechanisms and consequences

Materials Science and Technology ◽

10.1179/mst.1988.4.5.414 ◽

1988 ◽

Vol 4 (5) ◽

pp. 414-420 ◽

Author(s):

H. E. Evans

Keyword(s):

Stainless Steel ◽

Nuclear Fuel ◽

Fuel Cladding ◽

Nuclear Fuel Cladding

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The adsorption and desorption of water from a carbonaceous deposit layer on the surface of stainless steel representing spent AGR nuclear fuel cladding

Journal of Nuclear Science and Technology ◽

10.1080/00223131.2017.1403384 ◽

2017 ◽

Vol 55 (4) ◽

pp. 374-385 ◽

Author(s):

W. Stephen Walters ◽

Peter Durham ◽

Nicholas A. Hodge

Keyword(s):

Stainless Steel ◽

Nuclear Fuel ◽

Fuel Cladding ◽

Carbonaceous Deposit ◽

Adsorption And Desorption ◽

Nuclear Fuel Cladding ◽

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Prediction of Ballooning and Burst for Nuclear Fuel Cladding with Anisotropic Creep Modeling During Loss of Coolant Accident (LOCA)

Nuclear Engineering and Technology ◽

10.1016/j.net.2021.04.020 ◽

2021 ◽

Author(s):

Jinsu Kim ◽

Jeong Whan Yoon ◽

Hyochan Kim ◽

Sung-Uk Lee

Keyword(s):

Nuclear Fuel ◽

Fuel Cladding ◽

Loss Of Coolant Accident ◽

Loss Of Coolant ◽

Nuclear Fuel Cladding ◽

Anisotropic Creep

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Analysis of Cracking during Hot Isostatic Pressing of a Multi-metallic Layered Composite Nuclear Fuel Cladding Mother Tube

Transactions of the Korean Society of Mechanical Engineers A ◽

10.3795/ksme-a.2021.45.12.1057 ◽

2021 ◽

Vol 45 (12) ◽

pp. 1057-1065

Author(s):

Baosheng Bai ◽

Joonho Moon ◽

Michael P. Short ◽

Chi Bum Bahn

Keyword(s):

Nuclear Fuel ◽

Hot Isostatic Pressing ◽

Layered Composite ◽

Fuel Cladding ◽

Isostatic Pressing ◽

Nuclear Fuel Cladding ◽

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An advanced experimental design for modified burst testing of nuclear fuel cladding materials during transient loading

Annals of Nuclear Energy ◽

10.1016/j.anucene.2018.11.051 ◽

2019 ◽

Vol 127 ◽

pp. 30-38 ◽

Author(s):

M. Nedim Cinbiz ◽

Maxim Gussev ◽

Kory Linton ◽

Kurt A. Terrani

Keyword(s):

Experimental Design ◽

Nuclear Fuel ◽

Fuel Cladding ◽

Transient Loading ◽

Nuclear Fuel Cladding

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A Compton scattering based system for the examination of nuclear fuel cladding interface

2008 IEEE Nuclear Science Symposium Conference Record ◽

10.1109/nssmic.2008.4774082 ◽

2008 ◽

Author(s):

I. Yaar ◽

A. Givon ◽

B. Magoz ◽

I. Orion

Keyword(s):

Compton Scattering ◽

Nuclear Fuel ◽

Fuel Cladding ◽

Nuclear Fuel Cladding

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Chemistry of Nuclear Fuel Cladding in Light Water Reactors

Journal of the Atomic Energy Society of Japan ◽

10.3327/jaesjb.57.1_51 ◽

2015 ◽

Vol 57 (1) ◽

pp. 51-55

Author(s):

Toshiya KIDO

Keyword(s):

Nuclear Fuel ◽

Light Water Reactors ◽

Fuel Cladding ◽

Light Water ◽

Nuclear Fuel Cladding ◽

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Application of chemical interaction between (Fe, Cr) oxides and Mo oxide at high temperature for self-healing intelligence on nuclear fuel cladding in LWRs

Journal of Nuclear Science and Technology ◽

10.1080/00223131.2018.1512428 ◽

2018 ◽

Vol 55 (12) ◽

pp. 1402-1411 ◽

Author(s):

Zhengang Duan ◽

Huilong Yang ◽

Sho Kano ◽

John McGrady ◽

Hiroaki Abe

Keyword(s):

High Temperature ◽

Nuclear Fuel ◽

Chemical Interaction ◽

Self Healing ◽

Fuel Cladding ◽

Nuclear Fuel Cladding

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Influence of Processing Variables and Alloy Chemistry on the Corrosion Behavior of ZIRLO Nuclear Fuel Cladding

Zirconium in the Nuclear Industry: Eleventh International Symposium ◽

10.1520/stp16198s ◽

2009 ◽

pp. 710-710-16 ◽

Author(s):

RJ Comstock ◽

G Schoenberger ◽

GP Sabol

Keyword(s):

Nuclear Fuel ◽

Corrosion Behavior ◽

Fuel Cladding ◽

Alloy Chemistry ◽

Processing Variables ◽

Nuclear Fuel Cladding

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Observation of Tribologically Transformed Structures and fretting Wear Characteristics of Nuclear Fuel Cladding

Transactions of the Korean Society of Mechanical Engineers A ◽

10.3795/ksme-a.2002.26.12.2581 ◽

2002 ◽

Vol 26 (12) ◽

pp. 2581-2589

Keyword(s):

Nuclear Fuel ◽

Fretting Wear ◽

Fuel Cladding ◽

Wear Characteristics ◽

Nuclear Fuel Cladding

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Tensile Test Techniques for a Nuclear Fuel Cladding in a Hot Cell

The Mechanical Behavior of Materials X - Key Engineering Materials ◽

10.4028/0-87849-440-5.1561 ◽

2007 ◽

pp. 1561-1564

Author(s):

Do Sik Kim ◽

Sang Bok Ahn ◽

Wan Ho Oh ◽

Byung Ok Yoo ◽

Yong Sun Choo ◽

...

Keyword(s):

Tensile Test ◽

Nuclear Fuel ◽

Fuel Cladding ◽

Nuclear Fuel Cladding

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