A proposal to conduct a severe fuel damage experiment on an instrumented fuel assembly for the battelle full length high temperature test flht-6 PDF Download
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Author: R. D. Delaney
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Languages : en
Pages : 0
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Author: R. D. Delaney
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Author: R. D. Delaney
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Category :
Languages : en
Pages : 0
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Category : Power resources
Languages : en
Pages : 444
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Author:
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Category :
Languages : en
Pages : 108
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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%) 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.
Author:
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ISBN:
Category :
Languages : en
Pages : 117
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This report presents the final safety analysis for the preparation, conduct, and post-test discharge operation for the Full-Length High Temperature Experiment-5 (FLHT-5) to be conducted in the L-24 position of the National Research Universal (NRU) Reactor at Chalk River Nuclear Laboratories (CRNL), Ontario, Canada. The test is sponsored by an international group organized by the US Nuclear Regulatory Commission. The test is designed and conducted by staff from Pacific Northwest Laboratory with CRNL staff support. The test will study the consequences of loss-of-coolant and the progression of severe fuel damage.
Author: William N. Rausch
Publisher:
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Category :
Languages : en
Pages :
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Author: Donald D. Lanning
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Category :
Languages : en
Pages :
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Author: Z. R. Martinson
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Category :
Languages : en
Pages : 0
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This document describes the experiment operating specifications for test severe fuel damage 1-3 (sfd 1-3) to be conducted in the power burst facility (pbf) at the idaho national engineering laboratory (inel) as part of the nuclear regulatory commission's severe fuel damage research program. the overall experiment requirements and objectives for phase 1 of the sfd test series are described in the sfd experiment requirements document. the experiment specifications for test sfd 1-3 are described in the sfd experiment specification document and the pretest predictions are presented in the test sfd 1-3 experiment prediction document. the sfd test series objectives are to provide fuel bundle behavior data under severe high temperature flow starvation conditions. the objectives of test sfd 1-3 are to simulate the core heatup during the three mile island unit 2 accident and to characterize fuel rod damage, fission product release, and hydrogen production using high burnup test rods. a rod bundle consisting of 26 irradiated test fuel rods, two fully-instrumented fresh fuel rods, and four control rod guide thimbles will be tested in test sfd 1-3. the test will begin with a power calibration and preconditioning phase in which the bundle will be operated at a steady state bundle power of approximately 225 kw. after a 2 to 8 day shutdown period, high bundle temperatures of 2400 k will be obtained by operating with a bundle flow rate of 0.6 g/s and a maximum bundle power up to approximately 70 kw. the test will be terminated by a slow cooldown of the bundle with argon gas.
Author: L. W. Dickson
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ISBN:
Category :
Languages : en
Pages : 0
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Author: G. M. Hesson
Publisher:
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Category :
Languages : en
Pages : 99
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