THERMAL MARGIN EVALUATION FOR FELI FUEL ASSEMBLIES DURING AN ACCIDENTAL VESSEL DRAINING

Richard G. Ambrosek; Grant L. Hawkes; Fred W. Ingram; Jim W. Sterbentz

doi:10.1115/IMECE1999-1128

THERMAL MARGIN EVALUATION FOR FELI FUEL ASSEMBLIES DURING AN ACCIDENTAL VESSEL DRAINING

Richard G. Ambrosek
, Grant L. Hawkes
, Fred W. Ingram
, Jim W. Sterbentz

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

Abstract

Safety requirements many times require specific evaluations for experiment operating conditions during periods of postulated offnormal operation. A unique experimental facility in the Advanced Test Reactor was designed for enhancement of the neutron flux in an irradiation position, large "I", in the reflector region. Requirements for the facility necessitated analysis of the enhancement fuel to demonstrate that melting of the fuel element cladding would not occur during a loss of coolant event during reactor shutdown. The response of the fuel elements was evaluated using computer software that allowed detailed evaluations of the gamma heating magnitude and deposition fraction, natural convection cooling, prediction of heat transfer coefficients, and detailed finite element modeling for prediction of the temperature magnitudes and profile.

Original language	English
Title of host publication	Heat Transfer
Subtitle of host publication	Volume 4
Publisher	American Society of Mechanical Engineers (ASME)
Pages	275-282
Number of pages	8
ISBN (Electronic)	9780791826690
DOIs	https://doi.org/10.1115/IMECE1999-1128
State	Published - 1999
Externally published	Yes
Event	ASME 1999 International Mechanical Engineering Congress and Exposition, IMECE 1999 - Nashville, United States Duration: Nov 14 1999 → Nov 19 1999

Publication series

Name	ASME International Mechanical Engineering Congress and Exposition, Proceedings (IMECE)
Volume	1999-R

Conference

Conference	ASME 1999 International Mechanical Engineering Congress and Exposition, IMECE 1999
Country/Territory	United States
City	Nashville
Period	11/14/99 → 11/19/99

Access to Document

10.1115/IMECE1999-1128

Cite this

Ambrosek, R. G., Hawkes, G. L., Ingram, F. W., & Sterbentz, J. W. (1999). THERMAL MARGIN EVALUATION FOR FELI FUEL ASSEMBLIES DURING AN ACCIDENTAL VESSEL DRAINING. In Heat Transfer: Volume 4 (pp. 275-282). (ASME International Mechanical Engineering Congress and Exposition, Proceedings (IMECE); Vol. 1999-R). American Society of Mechanical Engineers (ASME). https://doi.org/10.1115/IMECE1999-1128

@inproceedings{de0eb0a4442c4b969b763468d45db09e,

title = "THERMAL MARGIN EVALUATION FOR FELI FUEL ASSEMBLIES DURING AN ACCIDENTAL VESSEL DRAINING",

abstract = "Safety requirements many times require specific evaluations for experiment operating conditions during periods of postulated offnormal operation. A unique experimental facility in the Advanced Test Reactor was designed for enhancement of the neutron flux in an irradiation position, large {"}I{"}, in the reflector region. Requirements for the facility necessitated analysis of the enhancement fuel to demonstrate that melting of the fuel element cladding would not occur during a loss of coolant event during reactor shutdown. The response of the fuel elements was evaluated using computer software that allowed detailed evaluations of the gamma heating magnitude and deposition fraction, natural convection cooling, prediction of heat transfer coefficients, and detailed finite element modeling for prediction of the temperature magnitudes and profile.",

author = "Ambrosek, \{Richard G.\} and Hawkes, \{Grant L.\} and Ingram, \{Fred W.\} and Sterbentz, \{Jim W.\}",

note = "Publisher Copyright: {\textcopyright} 1999 American Society of Mechanical Engineers (ASME). All rights reserved.; ASME 1999 International Mechanical Engineering Congress and Exposition, IMECE 1999 ; Conference date: 14-11-1999 Through 19-11-1999",

year = "1999",

doi = "10.1115/IMECE1999-1128",

language = "English",

series = "ASME International Mechanical Engineering Congress and Exposition, Proceedings (IMECE)",

publisher = "American Society of Mechanical Engineers (ASME)",

pages = "275--282",

booktitle = "Heat Transfer",

}

Ambrosek, RG, Hawkes, GL, Ingram, FW & Sterbentz, JW 1999, THERMAL MARGIN EVALUATION FOR FELI FUEL ASSEMBLIES DURING AN ACCIDENTAL VESSEL DRAINING. in Heat Transfer: Volume 4. ASME International Mechanical Engineering Congress and Exposition, Proceedings (IMECE), vol. 1999-R, American Society of Mechanical Engineers (ASME), pp. 275-282, ASME 1999 International Mechanical Engineering Congress and Exposition, IMECE 1999, Nashville, United States, 11/14/99. https://doi.org/10.1115/IMECE1999-1128

THERMAL MARGIN EVALUATION FOR FELI FUEL ASSEMBLIES DURING AN ACCIDENTAL VESSEL DRAINING. / Ambrosek, Richard G.; Hawkes, Grant L.; Ingram, Fred W. et al.
Heat Transfer: Volume 4. American Society of Mechanical Engineers (ASME), 1999. p. 275-282 (ASME International Mechanical Engineering Congress and Exposition, Proceedings (IMECE); Vol. 1999-R).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

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T1 - THERMAL MARGIN EVALUATION FOR FELI FUEL ASSEMBLIES DURING AN ACCIDENTAL VESSEL DRAINING

AU - Ambrosek, Richard G.

AU - Hawkes, Grant L.

AU - Ingram, Fred W.

AU - Sterbentz, Jim W.

PY - 1999

Y1 - 1999

N2 - Safety requirements many times require specific evaluations for experiment operating conditions during periods of postulated offnormal operation. A unique experimental facility in the Advanced Test Reactor was designed for enhancement of the neutron flux in an irradiation position, large "I", in the reflector region. Requirements for the facility necessitated analysis of the enhancement fuel to demonstrate that melting of the fuel element cladding would not occur during a loss of coolant event during reactor shutdown. The response of the fuel elements was evaluated using computer software that allowed detailed evaluations of the gamma heating magnitude and deposition fraction, natural convection cooling, prediction of heat transfer coefficients, and detailed finite element modeling for prediction of the temperature magnitudes and profile.

AB - Safety requirements many times require specific evaluations for experiment operating conditions during periods of postulated offnormal operation. A unique experimental facility in the Advanced Test Reactor was designed for enhancement of the neutron flux in an irradiation position, large "I", in the reflector region. Requirements for the facility necessitated analysis of the enhancement fuel to demonstrate that melting of the fuel element cladding would not occur during a loss of coolant event during reactor shutdown. The response of the fuel elements was evaluated using computer software that allowed detailed evaluations of the gamma heating magnitude and deposition fraction, natural convection cooling, prediction of heat transfer coefficients, and detailed finite element modeling for prediction of the temperature magnitudes and profile.

UR - https://www.scopus.com/pages/publications/85122766263

U2 - 10.1115/IMECE1999-1128

DO - 10.1115/IMECE1999-1128

M3 - Conference contribution

AN - SCOPUS:85122766263

T3 - ASME International Mechanical Engineering Congress and Exposition, Proceedings (IMECE)

SP - 275

EP - 282

BT - Heat Transfer

PB - American Society of Mechanical Engineers (ASME)

T2 - ASME 1999 International Mechanical Engineering Congress and Exposition, IMECE 1999

Y2 - 14 November 1999 through 19 November 1999

ER -

THERMAL MARGIN EVALUATION FOR FELI FUEL ASSEMBLIES DURING AN ACCIDENTAL VESSEL DRAINING

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