Advanced Search
DSpace@MIT

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

Research and Teaching Output of the MIT Community

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

Download
Author: Loomis, James North
Other Contributors: Massachusetts Institute of Technology. Dept. of Nuclear Engineering.
Advisor: Neil E. Todreas and William D. Hinkle.
Department: Massachusetts Institute of Technology. Dept. of Nuclear Engineering.
Publisher: Massachusetts Institute of Technology
Date Issued: 1981
Description:
Thesis (Nucl.E.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1981.MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE.Includes bibliographical references.
URI: http://hdl.handle.net/1721.1/15764
Keywords: Nuclear Engineering., Nuclear fuel elements Computer programs, Boiling water reactors Fluid dynamics, Boiling water reactors Thermal properties, Pressurized water reactors Fluid dynamics, Pressurized water reactors Thermal properties, Light water reactors Fluid dynamics, Light water reactors Thermal properties

Show full item metadata

Files in this item

Name Size Format Description
09520874.pdf 21.74Mb PDF Preview, non-printable (open to all)
09520874-MIT.pdf 21.74Mb PDF Full printable version (MIT only)

This item appears in the following Collection(s)

MIT-Mirage