Qualifying the codes and methodologies used for the evaluation of the BR2 core maximum nominal heat flux

Benoit Dionne; Constantine P. Tzanos; Arne P. Olson; John G. Stevens; Silva Kalcheva; Geert Van den Branden; Edgar Koonen

Qualifying the codes and methodologies used for the evaluation of the BR2 core maximum nominal heat flux

Benoit Dionne
, Constantine P. Tzanos
, Arne P. Olson
, John G. Stevens
, Silva Kalcheva
, Geert Van den Branden
, Edgar Koonen

Reactor Control and Experiments

Research output › peer-review

Original language	English
Title of host publication	Transactions of the American Nuclear Society
Publisher	American Nuclear Society
Pages	857-860
Number of pages	4
Volume	106
State	Published - 2012
Event	2012 ANS Annual Meeting and Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, NFSM 2012 - Chicago, IL Duration: 24 Jun 2012 → 28 Jun 2012

Publication series

Name	Transactions of the American Nuclear Society
Publisher	American Nuclear Society
ISSN (Print)	0003-018X

Conference

Conference	2012 ANS Annual Meeting and Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, NFSM 2012
Country/Territory	United States
City	Chicago, IL
Period	2012-06-24 → 2012-06-28

ASJC Scopus subject areas

Nuclear Energy and Engineering
Safety, Risk, Reliability and Quality

Cite this

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title = "Qualifying the codes and methodologies used for the evaluation of the BR2 core maximum nominal heat flux",

author = "Benoit Dionne and Tzanos, \{Constantine P.\} and Olson, \{Arne P.\} and Stevens, \{John G.\} and Silva Kalcheva and \{Van den Branden\}, Geert and Edgar Koonen",

year = "2012",

language = "English",

volume = "106",

series = "Transactions of the American Nuclear Society",

publisher = "American Nuclear Society",

pages = "857--860",

booktitle = "Transactions of the American Nuclear Society",

address = "United States",

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",

}

Dionne, B, Tzanos, CP, Olson, AP, Stevens, JG, Kalcheva, S , Van den Branden, G & Koonen, E 2012, Qualifying the codes and methodologies used for the evaluation of the BR2 core maximum nominal heat flux. in Transactions of the American Nuclear Society. vol. 106, Transactions of the American Nuclear Society, American Nuclear Society, pp. 857-860, 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, 2012-06-24.

TY - GEN

T1 - Qualifying the codes and methodologies used for the evaluation of the BR2 core maximum nominal heat flux

AU - Dionne, Benoit

AU - Tzanos, Constantine P.

AU - Olson, Arne P.

AU - Stevens, John G.

AU - Kalcheva, Silva

AU - Van den Branden, Geert

AU - Koonen, Edgar

PY - 2012

Y1 - 2012

UR - https://www.scopus.com/pages/publications/84876351239

M3 - In-proceedings paper

AN - SCOPUS:84876351239

VL - 106

T3 - Transactions of the American Nuclear Society

SP - 857

EP - 860

BT - Transactions of the American Nuclear Society

PB - 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 -