Improved multidimensional numerical methods for the steady state and transient thermal-hydraulic analysis of fuel pin bundles and nuclear reactor cores
Name
04401770.pdf
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9.01 MB
Format
Adobe PDF
Checksum (MD5)
7018d717c212744b00ac194db935086b
Author(s) •
Masterson, Robert Edward
Wolf Lothar
Date Issued
1977
Publisher
Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1977
Series/Report no.
MITNE ; no. 203
Description
Originally presented as the first author's thesis, (Sc. D.)--in the M.I.T. Dept. of Nuclear Engineering, 1977
Includes bibliographical references
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