Analytical model for transient gas flow in nuclear fuel rods. [PWR; BWR]
Journal Article
·
· Nucl. Technol.; (United States)
OSTI ID:5329164
An analytical model for calculating gas flow and pressure inside a nuclear fuel rod is presented. Such a model is required to calculate the pressure loading of cladding during ballooning that could occur for postulated reactor accidents. The mathematical model uses a porous media (permeability) concept to define the resistance to gas flow along the fuel rod. 7 refs.
- Research Organization:
- Row and Assoc, Bellevue, Wash, USA
- OSTI ID:
- 5329164
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 54:2; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
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·
Tue Jun 04 20:00:00 EDT 2019
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·
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·
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·
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