skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: LOFT fuel rod thermal/mechanical behavior predictions

Abstract

Best-estimate predictions of LOFT fuel rod behavior during the first LOFT nuclear test series have been made with both RELAP/FLOOD4/FRAP-T and RELAP/SCORE/MOXY computer code combinations. The purpose of the predictions are to test the best-estimate code accuracy by comparison of predictions to subsequent test data and to develop plans for post-test fuel replacements and examinations. The FRAP-T3 computer code was utilized which couples the thermal, mechanical, internal gas, and material property behavior of a nuclear rod during various postulated accident sequences. The cladding deformation models account for elastic-plastic behavior. FRAP-T3 requires coolant conditions to be specified as input boundary conditions. The coolant conditions for the blowdown and refill phases of a loss-of-coolant experiment (LOCE) were calculated with RELAP4/MOD6 and for the reflood portion with FLOOD4.

Authors:
; ;
Publication Date:
Research Org.:
Idaho National Engineering Lab., Idaho Falls (USA)
OSTI Identifier:
6588313
Report Number(s):
CONF-781105-6
TRN: 79-001114
DOE Contract Number:  
EY-76-C-07-1570
Resource Type:
Conference
Resource Relation:
Conference: ANS meeting, Washington, DC, USA, 12 Nov 1978
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; LOFT REACTOR; FUEL RODS; LOSS OF COOLANT; COMPUTER CALCULATIONS; FUEL ELEMENT FAILURE; MATHEMATICAL MODELS; PERFORMANCE; SIMULATION; ACCIDENTS; FUEL ELEMENTS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; TANK TYPE REACTORS; TEST REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220700* - Nuclear Reactor Technology- Plutonium & Isotope Production Reactors; 220600 - Nuclear Reactor Technology- Research, Test & Experimental Reactors

Citation Formats

Niebruegge, D A, Tolman, E L, and Solbrig, C W. LOFT fuel rod thermal/mechanical behavior predictions. United States: N. p., 1978. Web.
Niebruegge, D A, Tolman, E L, & Solbrig, C W. LOFT fuel rod thermal/mechanical behavior predictions. United States.
Niebruegge, D A, Tolman, E L, and Solbrig, C W. 1978. "LOFT fuel rod thermal/mechanical behavior predictions". United States. https://www.osti.gov/servlets/purl/6588313.
@article{osti_6588313,
title = {LOFT fuel rod thermal/mechanical behavior predictions},
author = {Niebruegge, D A and Tolman, E L and Solbrig, C W},
abstractNote = {Best-estimate predictions of LOFT fuel rod behavior during the first LOFT nuclear test series have been made with both RELAP/FLOOD4/FRAP-T and RELAP/SCORE/MOXY computer code combinations. The purpose of the predictions are to test the best-estimate code accuracy by comparison of predictions to subsequent test data and to develop plans for post-test fuel replacements and examinations. The FRAP-T3 computer code was utilized which couples the thermal, mechanical, internal gas, and material property behavior of a nuclear rod during various postulated accident sequences. The cladding deformation models account for elastic-plastic behavior. FRAP-T3 requires coolant conditions to be specified as input boundary conditions. The coolant conditions for the blowdown and refill phases of a loss-of-coolant experiment (LOCE) were calculated with RELAP4/MOD6 and for the reflood portion with FLOOD4.},
doi = {},
url = {https://www.osti.gov/biblio/6588313}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1978},
month = {1}
}

Conference:
Other availability
Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that hold this conference proceeding.

Save / Share: