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Title: PWR representative behavior during a LOCA

To date, there has been substantial analytical and experimental effort to define the margins between design basis loss-of-coolant accident (LOCA) behavior and regulatory limits on maximum fuel rod cladding temperature and deformation. As a result, there is extensive documentation on the modeling of fuel rod behavior in test reactors and design basis LOCA's. However, modeling of that behavior using representative, non-conservative, operating histories is not nearly as well documented in the public literature. Therefore, the objective of this paper is (a) to present calculations of LOCA induced behavior for Pressurized Water Reactor (PWR) core representative fuel rods, and (b) to discuss the variability in those calculations given the variability in fuel rod condition at the initiation of the LOCA. This analysis was limited to the study of changes in fuel rod behavior due to different power operating histories. The other two important parameters which affect that behavior, initial fuel rod design and LOCA coolant conditions were held invarient for all of the representative rods analyzed.
Authors:
Publication Date:
OSTI Identifier:
5918929
Report Number(s):
CONF-810803-3
ON: TI85004742
DOE Contract Number:
AC07-76ID01570
Resource Type:
Conference
Resource Relation:
Conference: Topical meeting on reactor safety aspects of fuel behavior, Sun Valley, ID, USA, 2 Aug 1981
Research Org:
Idaho National Engineering Lab., Idaho Falls (USA)
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; PWR TYPE REACTORS; FUEL RODS; LOSS OF COOLANT; BLOWDOWN; DEFORMATION; DESIGN BASIS ACCIDENTS; FUEL CANS; HEAT TRANSFER; HOT SPOTS; REACTOR ACCIDENTS; REACTOR CORES; REACTOR OPERATION; REACTOR SAFETY; TEMPERATURE MEASUREMENT; ACCIDENTS; ENERGY TRANSFER; FUEL ELEMENTS; OPERATION; REACTOR COMPONENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS 220900* -- Nuclear Reactor Technology-- Reactor Safety; 210200 -- Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled