Neutronic sensitivity studies on MEKIN, an accident analysis computer code for nuclear reactors
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)
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