SciTech Connect

Title: Full-length high-temperature severe fuel damage test No. 5

Full-length high-temperature severe fuel damage test No. 5 This report describes and presents data from a severe fuel damage test that was conducted in the National Research Universal (NRU) reactor at Chalk River Nuclear Laboratories (CRNL), Ontario, Canada. The test, designated FLHT-5, was the fourth in a series of full-length high-temperature (FLHT) tests on light-water reactor fuel. The tests were designed and performed by staff from the US Department of Energy`s Pacific Northwest Laboratory (PNL), operated by Battelle Memorial Institute. The test operation and test results are described in this report. The fuel bundle in the FLHT-5 experiment included 10 unirradiated full-length pressurized-water reactor (PWR) rods, 1 irradiated PWR rod and 1 dummy gamma thermometer. The fuel rods were subjected to a very low coolant flow while operating at low fission power. This caused coolant boilaway, rod dryout and overheating to temperatures above 2600 K, severe fuel rod damage, hydrogen generation, and fission product release. The test assembly and its effluent path were extensively instrumented to record temperatures, pressures, flow rates, hydrogen evolution, and fission product release during the boilaway/heatup transient. Post-test gamma scanning of the upper plenum indicated significant iodine and cesium release and deposition. Both stack gas activity and on-line gamma spectrometer data indicated significant ({approximately}50%) more » release of noble fission gases. Post-test visual examination of one side of the fuel bundle revealed no massive relocation and flow blockage; however, rundown of molten cladding was evident. « less
Authors: ; ; ; ; ;
Publication Date:
OSTI Identifier:OSTI ID: 10188341
Report Number(s):PNL--6540
ON: DE94001002; TRN: 93:024030
DOE Contract Number:AC06-76RL01830
Resource Type:Technical Report
Resource Relation:Other Information: PBD: Sep 1993
Research Org:Pacific Northwest Lab., Richland, WA (United States)
Sponsoring Org:USDOE, Washington, DC (United States)
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; DAMAGE; NRU REACTOR; TESTING; LOSS OF COOLANT; REACTOR SAFETY; HEAT TRANSFER; HYDRAULICS; FISSION PRODUCT RELEASE; FUEL CANS 220900; 210200; 220600; REACTOR SAFETY; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, NONBOILING WATER COOLED; RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS