Behavior of a Failed Fuel Rod During Film Boiling Operation. [PWR]. PDF Download
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Languages : en
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A single rod power-coolant-mismatch test (Test PCM-1) was conducted in the Power Burst Facility to evaluate the behavior of a pressurized water reactor (PWR)-type fuel rod subjected to film boiling operation at high power for a time exceeding that resulting in rod failure. The mechanisms of rod failure, the test rod response following failure, and the consequences of operation with a large molten fuel radius following fuel rod failure were investigated through destructive and nondestructive examination.
![Behavior of a Failed Fuel Rod During Film Boiling Operation. [PWR]. PDF](https://books.google.com/books/content/images/frontcover/pcyRAQAACAAJ?fife=w80-h100)
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Languages : en
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A single rod power-coolant-mismatch test (Test PCM-1) was conducted in the Power Burst Facility to evaluate the behavior of a pressurized water reactor (PWR)-type fuel rod subjected to film boiling operation at high power for a time exceeding that resulting in rod failure. The mechanisms of rod failure, the test rod response following failure, and the consequences of operation with a large molten fuel radius following fuel rod failure were investigated through destructive and nondestructive examination.
Author: Douglas W. Croucher
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Category : Nuclear fuel rods
Languages : en
Pages : 42
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Author: Douglas W. Croucher
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Category : Nuclear fuel rods
Languages : en
Pages : 44
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![Fuel Rod Failure During Film Boiling (PCM-1 Test in the PBF). [PWR]. PDF](https://books.google.com/books/content/images/frontcover/VQ1QAQAACAAJ?fife=w80-h100)
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Languages : en
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The Power-Cooling-Mismatch (PCM) Test, PCM-1 was conducted in the Power Burst Facility (PFB) in March of 1978. The PCM Test Series is being conducted at the Idaho National Engineering Laboratory by EG and G Idaho, Inc., under contract to the USNRC and is designed to characterize the behavior of nuclear fuel rods operating under conditions of high power or low coolant flow or both leading to departure from nucleate boiling. The PCM-1 test was performed to provide in-pile data for a ''worst case'' PCM incident. The objective of this experiment was to study the behavior of a single pressurized water reactor (PWR) fuel rod subjected to a high-power and low flow environment which would result in cladding failure at full power. The ''worst case'' conditions established for the experiment consisted of a rod peak power of 78.7 kW/m and a coolant mass flux of 1356 kg/s.m2. Fuel temperatures at the stipulated operating conditions were such that a significant volume of molten fuel was present when failure occurred which produced a high probability of molten fuel-coolant interaction (MFCI) with the possibility of a vapor explosion.
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Category : Nuclear fuel claddings
Languages : en
Pages : 72
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Author: Gary Lee Bennett
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Category : Water cooled reactors
Languages : en
Pages : 88
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Author: Robert Van Houten
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Category : Fuel burnup (Nuclear engineering)
Languages : en
Pages : 52
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Author:
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ISBN:
Category : Power resources
Languages : en
Pages : 500
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Author: United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development
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Category : Power resources
Languages : en
Pages : 1416
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Author: United States. Energy Research and Development Administration
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Category : Medicine
Languages : en
Pages : 906
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