Modular High-Temperature Gas-Cooled Reactor Short-Term Thermal Response to Flow and Reactivity Transients
Author:
Affiliation:
1. Oak Ridge National Laboratory, P.O. Box 2009, Oak Ridge, Tennessee 37831-8057
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/NT90-A34432
Reference4 articles.
1. The Performance of High-Temperature Reactor Fuel Particles at Extreme Temperatures
2. S. J. BALL, J. C. CLEVELAND, J. C. CONKLIN, and R. M. HARRINGTON, “High-Temperature Gas-Cooled Reactor Safety Studies for the Division of RSR Quarterly Progress Report,” ORNL/NUREG/TM-397, Oak Ridge National Laboratory (Jan. 1-Mar. 31, 1980).
3. J. C. CLEVELAND, “Modular High-Temperature Gas-Cooled Reactor Short Term Thermal Response to Flow and Reactivity Transients,” ORNL/TM-11074, Oak Ridge National Laboratory (in preparation).
4. J. C. CLEVELAND, “CORTAP: A Coupled Neutron Kinetics-Heat Transfer Computer Program for the Dynamic Simulation of the High-Temperature Gas-Cooled Reactor Core,” ORNL/NUREG/TM-39, Oak Ridge National Laboratory (Jan. 1977).
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