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

Thesis (Nucl.E.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1981. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Includes bibliographical references. / by James North Loomis. / Nucl.E.

Identiferoai:union.ndltd.org:MIT/oai:dspace.mit.edu:1721.1/15764
Date January 1981
CreatorsLoomis, James North
ContributorsNeil E. Todreas and William D. Hinkle., Massachusetts Institute of Technology. Dept. of Nuclear Engineering., Massachusetts Institute of Technology. Department of Nuclear Engineering, Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
PublisherMassachusetts Institute of Technology
Source SetsM.I.T. Theses and Dissertation
LanguageEnglish
Detected LanguageEnglish
TypeThesis
Format2 v. ([572] leaves), 22797335 bytes, 22797093 bytes, application/pdf, application/pdf, application/pdf
RightsM.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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