Improvement of Critical Heat Flux Correlation for Research Reactors using Plate-Type Fuel
Author:
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
http://www.tandfonline.com/doi/pdf/10.1080/18811248.1998.9733966
Reference10 articles.
1. Analytical Study on Thermal-Hydraulic Behavior of Transient from Forced Circulation to Natural Circulation in JRR-3
2. Experimental Study of Differences in DNB Heat Flux between Upflow and Downflow in Vertical Rectangular Channel
3. A New CHF Correlation Scheme Proposed for Vertical Rectangular Channels Heated From Both Sides in Nuclear Research Reactors
4. Core Thermohydraulic Design with 20% LEU Fuel for Upgraded Research Reactor JRR-3
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