Improved multidimensional numerical methods for the steady state and transient thermal-hydraulic analysis of fuel pin bundles and nuclear reactor cores
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Massachusetts Institute of Technology. Department of Nuclear Engineering
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Originally presented as the first author's thesis, (Sc. D.)--in the M.I.T. Dept. of Nuclear Engineering, 1977 Includes bibliographical references
Date issued
1977Publisher
Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1977
Series/Report no.
MITNE ; no. 203