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A METHOD FOR MEASURING THERMAL CONDUCTIVITY OF URANIUM-DIOXIDE AT HIGH TEMPERATURES UNDER SIMULATED IN-REACTOR CONDITIONSHimes, David Arthur January 1979 (has links)
No description available.
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An investigation into the effect of fuel pellet eccentricity on fuel-cladding gap heat transferGoldberg, Marc David 08 1900 (has links)
No description available.
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High temperature thermal conductivity measurements of UO₂ by direct electrical heatingBassett, Britt January 1980 (has links)
No description available.
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Thermal/hydraulic analysis methods for PWR'sMoreno Palacios, Pablo January 1976 (has links)
Thesis. 1976. Nucl.E.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering. / Microfiche copy available in Archives and Science. / Includes bibliographical references. / by Pablo Moreno. / Nucl.E.
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Improved multidimensional numerical methods for the steady state and transient thermal-hydraulic analysis of fuel pin bundles and nuclear reactor cores.Masterson, Robert Edward. January 1977 (has links)
Thesis: Sc. D., Massachusetts Institute of Technology, Department of Nuclear Engineering, 1977 / Includes bibliographical references. / Sc. D. / Sc. D. Massachusetts Institute of Technology, Department of Nuclear Engineering
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Thermal-hydraulic analysis of tight lattice light water reactors.Boyd, William Artis January 1977 (has links)
Thesis. 1977. M.S.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Includes bibiliographical references. / M.S.
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A hydrodynamic evaluation of the Sandia UO₂ equation of state experimentSmith, Mark Scott January 1981 (has links)
No description available.
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Comparison of conservative and best estimate heat transfer packages with COBRA-IV-I.Massoud, Mahmoud January 1978 (has links)
Thesis. 1978. Nucl.E.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering. / MICOFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Includes bibliographical references. / Nucl.E.
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Sensitivity study of the assembly averaged thermal-hydraulic models of the MEKIN computer code in power transientsRodack, Thomas January 1977 (has links)
Thesis (Nucl. E.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering; and, (M.S.)--Massachusetts Institute of Technology, Dept. of Mechanical Engineering, 1977. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Includes bibliographical references. / by Thomas Rodack. / M.S. / Nucl.E.
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