Comparative evaluation of fuel element heat conduction models
Abstract
Computer codes that predict thermal-hydraulic performance in light water reactors are found to employ a variety of conduction heat transfer models for the determination of the temperature distribution within fuel elements. The objective of this study was to evaluate, in a consistent manner, the relative merits of these various fuel element conduction heat transfer models by comparing accuracy, speed, and computer storage requirements for calculations performed on selected reference or benchmark problems. Methods of particular interest include: (1) implicit finite difference method (FDM) in COBRA-IIIC; (2) weighted residuals method (WRM) in COBRA-IV; (3) nodal integral method (NIM) in TRAC-PF1; and (4) control volume method (CVM) in RELAP5/MOD1.
- Authors:
- Publication Date:
- Research Org.:
- Univ. of Florida, Gainesville
- OSTI Identifier:
- 6885471
- Report Number(s):
- CONF-860610-
Journal ID: CODEN: TANSA; TRN: 87-016207
- Resource Type:
- Conference
- Journal Name:
- Trans. Am. Nucl. Soc.; (United States)
- Additional Journal Information:
- Journal Volume: 52; Conference: American Nuclear Society annual meeting, Reno, NV, USA, 15 Jun 1986
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 42 ENGINEERING; BWR TYPE REACTORS; HEAT TRANSFER; HYDRAULICS; MATHEMATICAL MODELS; COMPARATIVE EVALUATIONS; PWR TYPE REACTORS; ACCURACY; BENCHMARKS; DISCRETE ORDINATE METHOD; EFFICIENCY; FINITE DIFFERENCE METHOD; FUEL ELEMENTS; PERFORMANCE; STEADY-STATE CONDITIONS; TRANSIENTS; ENERGY TRANSFER; FLUID MECHANICS; ITERATIVE METHODS; MECHANICS; NUMERICAL SOLUTION; REACTOR COMPONENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 210100* - Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled; 420400 - Engineering- Heat Transfer & Fluid Flow
Citation Formats
Panicker, M, Dugan, E T, and Anghaie, S. Comparative evaluation of fuel element heat conduction models. United States: N. p., 1986.
Web.
Panicker, M, Dugan, E T, & Anghaie, S. Comparative evaluation of fuel element heat conduction models. United States.
Panicker, M, Dugan, E T, and Anghaie, S. 1986.
"Comparative evaluation of fuel element heat conduction models". United States.
@article{osti_6885471,
title = {Comparative evaluation of fuel element heat conduction models},
author = {Panicker, M and Dugan, E T and Anghaie, S},
abstractNote = {Computer codes that predict thermal-hydraulic performance in light water reactors are found to employ a variety of conduction heat transfer models for the determination of the temperature distribution within fuel elements. The objective of this study was to evaluate, in a consistent manner, the relative merits of these various fuel element conduction heat transfer models by comparing accuracy, speed, and computer storage requirements for calculations performed on selected reference or benchmark problems. Methods of particular interest include: (1) implicit finite difference method (FDM) in COBRA-IIIC; (2) weighted residuals method (WRM) in COBRA-IV; (3) nodal integral method (NIM) in TRAC-PF1; and (4) control volume method (CVM) in RELAP5/MOD1.},
doi = {},
url = {https://www.osti.gov/biblio/6885471},
journal = {Trans. Am. Nucl. Soc.; (United States)},
number = ,
volume = 52,
place = {United States},
year = {Wed Jan 01 00:00:00 EST 1986},
month = {Wed Jan 01 00:00:00 EST 1986}
}