Computer modeling of transport of oxidizing species in grain boundaries during zirconium corrosion

Xian Ming Bai; Yongfeng Zhang; Michael Tonks

Computer modeling of transport of oxidizing species in grain boundaries during zirconium corrosion

Xian Ming Bai, Yongfeng Zhang, Michael Tonks

Materials Research Institute (MRI)

Research output: Contribution to journal › Conference article › peer-review

Original language	English (US)
Number of pages	1
Journal	Transactions of the American Nuclear Society
Volume	110
State	Published - Jan 1 2014
Event	2014 Annual Meeting on Transactions of the American Nuclear Society and Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, NSFM 2014 - Reno, NV, United States Duration: Jun 15 2014 → Jun 19 2014

All Science Journal Classification (ASJC) codes

Nuclear Energy and Engineering
Safety, Risk, Reliability and Quality

Cite this

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title = "Computer modeling of transport of oxidizing species in grain boundaries during zirconium corrosion",

author = "Bai, {Xian Ming} and Yongfeng Zhang and Michael Tonks",

year = "2014",

month = jan,

day = "1",

language = "English (US)",

volume = "110",

journal = "Transactions of the American Nuclear Society",

issn = "0003-018X",

publisher = "American Nuclear Society",

note = "2014 Annual Meeting on Transactions of the American Nuclear Society and Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, NSFM 2014 ; Conference date: 15-06-2014 Through 19-06-2014",

}

TY - JOUR

T1 - Computer modeling of transport of oxidizing species in grain boundaries during zirconium corrosion

AU - Bai, Xian Ming

AU - Zhang, Yongfeng

AU - Tonks, Michael

PY - 2014/1/1

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M3 - Conference article

AN - SCOPUS:84904633855

SN - 0003-018X

VL - 110

JO - Transactions of the American Nuclear Society

JF - Transactions of the American Nuclear Society

T2 - 2014 Annual Meeting on Transactions of the American Nuclear Society and Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, NSFM 2014

Y2 - 15 June 2014 through 19 June 2014

ER -

Computer modeling of transport of oxidizing species in grain boundaries during zirconium corrosion

All Science Journal Classification (ASJC) codes

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Cite this