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Title: Critical heat flux in natural convection cooled TRIGA reactors with hexagonal bundle

Abstract

A three-rod bundle Critical Heat Flux (CHF) study at low flow, low pressure, and natural convection condition has been conducted, simulating TRIGA reactors with the hexagonally configured core. The test section is a custom-made trefoil shape tube with three identical fuel pin heater rods located symmetrically inside. The full scale fuel rod is electrically heated with a chopped-cosine axial power profile. CHF experiments were carried out with the following conditions: inlet water subcooling from 30 K to 95 K; pressure from 110 kPa to 230 kPa; mass flux up to 150 kg/m{sup 2}s. About 50 CHF data points were collected and compared with a few existing CHF correlations whose application ranges are close to the testing conditions. Some tests were performed with the forced convection to identify the potential difference between the CHF under the natural convection and forced convection. The relevance of the CHF to test parameters is investigated. (authors)

Authors:
; ; ; ;  [1]; ; ;  [2]
  1. Univ. of Wisconsin-Madison, 1500 Engineering Drive, Madison, WI 53706 (United States)
  2. Argonne National Laboratory, 9700 S. Cass Avenue, Argonne, IL 60439 (United States)
Publication Date:
Research Org.:
American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
OSTI Identifier:
22107836
Resource Type:
Conference
Resource Relation:
Conference: ICAPP '12: 2012 International Congress on Advances in Nuclear Power Plants, Chicago, IL (United States), 24-28 Jun 2012; Other Information: Country of input: France; 10 refs.; Related Information: In: Proceedings of the 2012 International Congress on Advances in Nuclear Power Plants - ICAPP '12| 2799 p.
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; CRITICAL HEAT FLUX; FORCED CONVECTION; FUEL ELEMENT CLUSTERS; FUEL PINS; FUEL RODS; NATURAL CONVECTION; NUCLEAR POWER PLANTS; SUBCOOLING; TESTING; TRIGA TYPE REACTORS; WATER

Citation Formats

Yang, J., Avery, M., De Angelis, M., Anderson, M., Corradini, M., Feldman, E. E., Dunn, F. E., and Matos, J. E. Critical heat flux in natural convection cooled TRIGA reactors with hexagonal bundle. United States: N. p., 2012. Web.
Yang, J., Avery, M., De Angelis, M., Anderson, M., Corradini, M., Feldman, E. E., Dunn, F. E., & Matos, J. E. Critical heat flux in natural convection cooled TRIGA reactors with hexagonal bundle. United States.
Yang, J., Avery, M., De Angelis, M., Anderson, M., Corradini, M., Feldman, E. E., Dunn, F. E., and Matos, J. E. Sun . "Critical heat flux in natural convection cooled TRIGA reactors with hexagonal bundle". United States.
@article{osti_22107836,
title = {Critical heat flux in natural convection cooled TRIGA reactors with hexagonal bundle},
author = {Yang, J. and Avery, M. and De Angelis, M. and Anderson, M. and Corradini, M. and Feldman, E. E. and Dunn, F. E. and Matos, J. E.},
abstractNote = {A three-rod bundle Critical Heat Flux (CHF) study at low flow, low pressure, and natural convection condition has been conducted, simulating TRIGA reactors with the hexagonally configured core. The test section is a custom-made trefoil shape tube with three identical fuel pin heater rods located symmetrically inside. The full scale fuel rod is electrically heated with a chopped-cosine axial power profile. CHF experiments were carried out with the following conditions: inlet water subcooling from 30 K to 95 K; pressure from 110 kPa to 230 kPa; mass flux up to 150 kg/m{sup 2}s. About 50 CHF data points were collected and compared with a few existing CHF correlations whose application ranges are close to the testing conditions. Some tests were performed with the forced convection to identify the potential difference between the CHF under the natural convection and forced convection. The relevance of the CHF to test parameters is investigated. (authors)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2012},
month = {7}
}

Conference:
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