Improved multidimensional numerical methods for the steady state and transient thermal-hydraulic analysis of fuel pin bundles and nuclear reactor cores
Originally presented as the first author's thesis, (Sc. D.)--in the M.I.T. Dept. of Nuclear Engineering, 1977
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Format: | Technical Report |
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Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1977
2014
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Online Access: | http://hdl.handle.net/1721.1/89506 |