Modeling constituent redistribution in U-Pu-Zr metallic fuel using the advanced fuel performance code bison

Jack Galloway; Cetin Unal; Neil Carlson; Douglas Porter; Steve Hayes

Modeling constituent redistribution in U-Pu-Zr metallic fuel using the advanced fuel performance code bison

Jack Galloway
, Cetin Unal
, Neil Carlson
, Douglas Porter
, Steve Hayes

Nuclear Fuels & Materials

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

Original language	English
Pages (from-to)	922-924
Number of pages	3
Journal	Transactions of the American Nuclear Society
Volume	110
State	Published - 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

Cite this

@article{5bbf486d064a4925a5f101249e801047,

title = "Modeling constituent redistribution in U-Pu-Zr metallic fuel using the advanced fuel performance code bison",

author = "Jack Galloway and Cetin Unal and Neil Carlson and Douglas Porter and Steve Hayes",

year = "2014",

language = "English",

volume = "110",

pages = "922--924",

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 - Modeling constituent redistribution in U-Pu-Zr metallic fuel using the advanced fuel performance code bison

AU - Galloway, Jack

AU - Unal, Cetin

AU - Carlson, Neil

AU - Porter, Douglas

AU - Hayes, Steve

PY - 2014

Y1 - 2014

UR - https://www.scopus.com/pages/publications/84904658956

M3 - Conference article

AN - SCOPUS:84904658956

SN - 0003-018X

VL - 110

SP - 922

EP - 924

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 -

Modeling constituent redistribution in U-Pu-Zr metallic fuel using the advanced fuel performance code bison

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