Full-length High-temperature Severe Fuel Damage Test #5 PDF Download
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Author: Donald D. Lanning
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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: William N. Rausch
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Category :
Languages : en
Pages :
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Author: G. M. Hesson
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Category :
Languages : en
Pages : 99
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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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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: David A. Petti
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Category : Government publications
Languages : en
Pages : 512
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Author:
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Category : Power resources
Languages : en
Pages : 906
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Semiannual, with semiannual and annual indexes. References to all scientific and technical literature coming from DOE, its laboratories, energy centers, and contractors. Includes all works deriving from DOE, other related government-sponsored information, and foreign nonnuclear information. Arranged under 39 categories, e.g., Biomedical sciences, basic studies; Biomedical sciences, applied studies; Health and safety; and Fusion energy. Entry gives bibliographical information and abstract. Corporate, author, subject, report number indexes.
Author: R. D. Delaney
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Category :
Languages : en
Pages : 0
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Author: United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development
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Category : Nature
Languages : en
Pages : 2480
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Author: D. D. Lanning
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Category :
Languages : en
Pages : 0
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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 u.s. 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. an array of full-length lwr fuel rods will be subjected to conditions that simulate loss-of-coolant flow at decay-heat power level. the 12-position array includes one pre-irradiated pwr rod, 10 fresh fuel rods, and one instrument thimble containing a dummy steel rod. the boilaway of the coolant will permit heatup of the rods to the point of rapid cladding oxidation with concomitant cladding melting, partial fuel liquefaction, fuel oxidation, hydrogen generation, and fission product release. the hydrogen generation (from the oxidation reaction), the bundle temperatures, the liquid level, and the fission product release will be monitored during the test. the melt progression will be assessed using post test visual and metallographic examination results. experience from similar flht tests is combined with analysis results to show that: 1) high-temperature material will be contained within the shroud that surrounds the rod array, precluding damage to the nru loop pressure tube; 2) the released fission products and hydrogen will be contained and disposed of by the effluent control system in a manner that poses no unresolved safety hazard to operating personnel or to the public; and 3) the radiation exposure to operating personnel and to the public will remain below approved control limits.
