Oxidation Studies on NBG-18 Grade Nuclear Graphite

J. Kane; C. Karthik; D. P. Butt; W. E. Windes; Rick Ubic; Karthik Chinnathambi

Oxidation Studies on NBG-18 Grade Nuclear Graphite

J. Kane, C. Karthik, D. P. Butt, W. E. Windes, Rick Ubic, Karthik Chinnathambi

Micron School of Materials Science and Engineering

Research output: Contribution to journal › Article › peer-review

1 Scopus citations

Abstract

In this work we focus on the oxidation of grade NBG-18 nuclear graphite in oxygen/nitrogen atmospheres. NBG-18 was chosen because of its potential use in high dosage regions of the pebble bed concept VHTR.

Original language	American English
Journal	Transactions of the American Nuclear Society
State	Published - 1 Jan 2011

Keywords

fission reactor fuel
gas cooled reactors
oxidation

EGS Disciplines

Materials Science and Engineering

Cite this

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title = "Oxidation Studies on NBG-18 Grade Nuclear Graphite",

abstract = "In this work we focus on the oxidation of grade NBG-18 nuclear graphite in oxygen/nitrogen atmospheres. NBG-18 was chosen because of its potential use in high dosage regions of the pebble bed concept VHTR.",

keywords = "fission reactor fuel, gas cooled reactors, oxidation",

author = "J. Kane and C. Karthik and Butt, {D. P.} and Windes, {W. E.} and Rick Ubic and Karthik Chinnathambi",

year = "2011",

month = jan,

day = "1",

language = "American English",

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TY - JOUR

T1 - Oxidation Studies on NBG-18 Grade Nuclear Graphite

AU - Kane, J.

AU - Karthik, C.

AU - Butt, D. P.

AU - Windes, W. E.

AU - Ubic, Rick

AU - Chinnathambi, Karthik

PY - 2011/1/1

Y1 - 2011/1/1

N2 - In this work we focus on the oxidation of grade NBG-18 nuclear graphite in oxygen/nitrogen atmospheres. NBG-18 was chosen because of its potential use in high dosage regions of the pebble bed concept VHTR.

AB - In this work we focus on the oxidation of grade NBG-18 nuclear graphite in oxygen/nitrogen atmospheres. NBG-18 was chosen because of its potential use in high dosage regions of the pebble bed concept VHTR.

KW - fission reactor fuel

KW - gas cooled reactors

KW - oxidation

UR - https://scholarworks.boisestate.edu/mse_facpubs/142

M3 - Article

SN - 0003-018X

JO - Transactions of the American Nuclear Society

JF - Transactions of the American Nuclear Society

ER -

Oxidation Studies on NBG-18 Grade Nuclear Graphite

Abstract

Keywords

EGS Disciplines

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