Neutronic sensitivity studies on MEKIN, an accident analysis computer code for nuclear reactors
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Alternative title
Accident analysis computer code for nuclear reactors
Other Contributors
Massachusetts Institute of Technology. Department of Nuclear Engineering
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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)
Date issued
1977Publisher
Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1977
Series/Report no.
MITNE ; no. 207