Determination of Transient Radial-Azimuthal Temperature Distributions in Fuel Bundles Under Loss-of-Coolant-Accident Conditions
Author:
Affiliation:
1. The Ohio State University Department of Mechanical Engineering, Nuclear Engineering Program 206 West 18th Avenue, Columbus, Ohio 43210
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT88-A34178
Reference22 articles.
1. R. T. LAHEY, Jr. and F. J. MOODY, The Thermal-Hydraulics of a Boiling Water Nuclear Reactor, American Nuclear Society, La Grange Park, Illinois (1979).
2. A general one-dimensional model for conduction-controlled rewetting of a surface
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