Author: G. M. Hesson
Publisher:
ISBN:
Category :
Languages : en
Pages : 99
Book Description
Full-length High-temperature Severe Fuel Damage Test #2
Power Burst Facility (PBF) Severe Fuel Damage Test 1-4
Author: David A. Petti
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 512
Book Description
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 512
Book Description
Full-length High-temperature Severe Fuel Damage Test
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 108
Book Description
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.
Publisher:
ISBN:
Category :
Languages : en
Pages : 108
Book Description
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.
Energy Research Abstracts
High Temperature Alloys for Gas Turbines and Other Applications, 1986
Author: W. Betz
Publisher: Springer Science & Business Media
ISBN: 9789027723482
Category : Gas-turbines
Languages : en
Pages : 888
Book Description
Publisher: Springer Science & Business Media
ISBN: 9789027723482
Category : Gas-turbines
Languages : en
Pages : 888
Book Description
Energy and Water Development Appropriations for 1993
Author: United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development
Publisher:
ISBN:
Category : Nature
Languages : en
Pages : 2480
Book Description
Publisher:
ISBN:
Category : Nature
Languages : en
Pages : 2480
Book Description
Forging, Stamping, Heat Treating
Proceedings of the International Meeting on Thermal Nuclear Reactor Safety
Author:
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 720
Book Description
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 720
Book Description
Full-Length High-Temperature Severe Fuel Damage Test No. 5
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 117
Book Description
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.
Publisher:
ISBN:
Category :
Languages : en
Pages : 117
Book Description
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.