Finite volume method based neutronic solvers for steady and transient analysis of molten salt reactors

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

Original language	English
Pages (from-to)	767-769
Number of pages	3
Journal	Transactions of the American Nuclear Society
Volume	114
Issue number	1
State	Published - 2016
Event	2016 Transactions of the American Nuclear Society Annual Meeting, ANS 2016 - New Orleans, United States Duration: 12 Jun 2016 → 16 Jun 2016

Cite this

@article{0b7665ef192a4d40a5e8a0986d4b305b,

title = "Finite volume method based neutronic solvers for steady and transient analysis of molten salt reactors",

author = "Liangzhi Cao and Tianliang Hu and Hongchun Wu",

year = "2016",

language = "英语",

volume = "114",

pages = "767--769",

journal = "Transactions of the American Nuclear Society",

issn = "0003-018X",

publisher = "American Nuclear Society",

number = "1",

note = "2016 Transactions of the American Nuclear Society Annual Meeting, ANS 2016 ; Conference date: 12-06-2016 Through 16-06-2016",

}

TY - JOUR

T1 - Finite volume method based neutronic solvers for steady and transient analysis of molten salt reactors

AU - Cao, Liangzhi

AU - Hu, Tianliang

AU - Wu, Hongchun

PY - 2016

Y1 - 2016

UR - https://www.scopus.com/pages/publications/85117941309

M3 - 会议文章

AN - SCOPUS:85117941309

SN - 0003-018X

VL - 114

SP - 767

EP - 769

JO - Transactions of the American Nuclear Society

JF - Transactions of the American Nuclear Society

IS - 1

T2 - 2016 Transactions of the American Nuclear Society Annual Meeting, ANS 2016

Y2 - 12 June 2016 through 16 June 2016

ER -