U-Pu-Zr fuel properties and thermal performance modeling for sodium fast reactors

Wenzhong Zhou; Cetin Unal

U-Pu-Zr fuel properties and thermal performance modeling for sodium fast reactors

Wenzhong Zhou
, Cetin Unal

Research output: Journal Publications and Reviews › RGC 21 - Publication in refereed journal › peer-review

Original language	English
Journal	Transactions of the American Nuclear Society
Volume	106
Publication status	Published - 2012
Externally published	Yes
Event	2012 ANS Annual Meeting and Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, NFSM 2012 - Chicago, IL, United States Duration: 24 Jun 2012 → 28 Jun 2012

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@article{f6acae70d3c24f18b5768fd70f70f188,

title = "U-Pu-Zr fuel properties and thermal performance modeling for sodium fast reactors",

author = "Wenzhong Zhou and Cetin Unal",

year = "2012",

language = "English",

volume = "106",

journal = "Transactions of the American Nuclear Society",

issn = "0003-018X",

publisher = "American Nuclear Society",

note = "2012 ANS Annual Meeting and Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, NFSM 2012 ; Conference date: 24-06-2012 Through 28-06-2012",

}

TY - JOUR

T1 - U-Pu-Zr fuel properties and thermal performance modeling for sodium fast reactors

AU - Zhou, Wenzhong

AU - Unal, Cetin

PY - 2012

Y1 - 2012

UR - https://www.scopus.com/pages/publications/84876394236

UR - https://www.scopus.com/record/pubmetrics.uri?eid=2-s2.0-84876394236&origin=recordpage

M3 - RGC 21 - Publication in refereed journal

SN - 0003-018X

VL - 106

JO - Transactions of the American Nuclear Society

JF - Transactions of the American Nuclear Society

T2 - 2012 ANS Annual Meeting and Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, NFSM 2012

Y2 - 24 June 2012 through 28 June 2012

ER -

U-Pu-Zr fuel properties and thermal performance modeling for sodium fast reactors

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