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Department of Nuclear Science and Engineering
Dept. of Nuclear Engineering Technical Reports
Neutronic sensitivity studies on MEKIN, an accident analysis computer code for nuclear reactors
Neutronic sensitivity studies on MEKIN, an accident analysis computer code for nuclear reactors
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Name
04399028.pdf
Size
7.15 MB
Format
Adobe PDF
Checksum
(MD5)
f21cafd865c6fdf0f1edc2f7441d8016
Author(s)
Barbehenn, Craig Edwin
•
Lanning David D.
Alternative Title
Accident analysis computer code for nuclear reactors
Date Issued
1977
Publisher
Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1977
Series/Report no.
MITNE ; no. 207
Description
Originally presented as the first author's thesis, (Nucl. E.)--in the M.I.T. Dept. of Nuclear Engineering, 1977
Includes bibliographical references (pages 122-123)
Persistent DSpace Link
http://hdl.handle.net/1721.1/89505
