Behavior of Defective PWR Fuel Rods During Power Ramp and Film Boiling Operation PDF Download
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Author: Douglas W. Croucher
Publisher:
ISBN:
Category : Nuclear fuel rods
Languages : en
Pages : 44
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Book Description
Author: Douglas W. Croucher
Publisher:
ISBN:
Category : Nuclear fuel rods
Languages : en
Pages : 44
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Book Description
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 520
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Book Description
![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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Category :
Languages : en
Pages :
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Book Description
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: U.S. Nuclear Regulatory Commission
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 148
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Author:
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ISBN:
Category :
Languages : en
Pages : 598
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Author:
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Category : Nuclear power plants
Languages : en
Pages : 880
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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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Category :
Languages : en
Pages :
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Book Description
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.
Author: U.S. Nuclear Regulatory Commission. Division of Technical Information and Document Control
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 378
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Book Description
Includes indexes.
Author: U.S. Nuclear Regulatory Commission. Policy and Publications Management Branch
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 380
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Book Description
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1692
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