Reactor thermal-hydraulic analysis improvement and application of the code COBRA-IIIC/MIT

Author(s)
Loomis, James North
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Massachusetts Institute of Technology. Dept. of Nuclear Engineering.
Advisor
Neil E. Todreas and William D. Hinkle.
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M.I.T. theses are protected by copyright. They may be viewed from this source for any purpose, but reproduction or distribution in any format is prohibited without written permission. See provided URL for inquiries about permission. http://dspace.mit.edu/handle/1721.1/7582
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Description
Thesis (Nucl.E.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1981.
 
MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE.
 
Includes bibliographical references.
 
Date issued
1981
URI
http://hdl.handle.net/1721.1/15764
Department
Massachusetts Institute of Technology. Department of Nuclear Engineering; Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
Publisher
Massachusetts Institute of Technology
Keywords
Nuclear Engineering.
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