Rewetting Analysis of a Pressurized Water Reactor Fuel Slab Using Improved Lumped Models
Author:
Affiliation:
1. Nuclebras Equipamentos Pesados S.A., Rio de Janeiro 23825-410, Brazil
2. Nuclear Engineering Program, COPPE, Universidade Federal do Rio de Janeiro, COPPE, CP 68509, Rio de Janeiro 21941-972, Brazil
Abstract
Publisher
ASME International
Subject
Nuclear Energy and Engineering,Radiation
Link
http://asmedigitalcollection.asme.org/nuclearengineering/article-pdf/7/4/041604/6741179/ners_007_04_041604.pdf
Reference22 articles.
1. A Three-Region Conduction-Controlled Rewetting Analysis by the Heat Balance Integral Method;Int. J. Therm. Sci.,2009
2. An Analysis of Rewetting of a Nuclear Fuel Rod in Water Reactor Emergency Core Cooling;Nucl. Eng. Des.,1975
3. Method of Solving the Potential Field in Complicated Geometries and the Potential Flow in the Lower Plenum of a Pressurized Water Reactor;Nucl. Eng. Des.,1975
4. An Analytical Solution to Fuel-and-Cladding Model of the Rewetting of a Nuclear Fuel Rod;Nucl. Eng. Des.,1980
5. Solution to a Fuel-and-Cladding Rewetting Model;Int. Comm. Heat Mass Transfer,1989
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