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University of Michigan. Dept. of Nuclear Engineering

  • A (p-¹¹B) fueled mirror fusion reactorA (p-¹¹B) fueled mirror fusion reactor
  • A comparative study of reactor core meltdown and the assessment of post accident heat removalA comparative study of reactor core meltdown and the assessment of post accident heat removal
  • A comparison of seismic risk studies in nuclear power plantsA comparison of seismic risk studies in nuclear power plants
  • A comparison of the heat transport effectiveness of some coolants and homogeneous fuels used in the primary loop of nuclear powerplantsA comparison of the heat transport effectiveness of some coolants and homogeneous fuels used in the primary loop of nuclear powerplants
  • A comparison of the Westinghouse and General Electric thermal design basesA comparison of the Westinghouse and General Electric thermal design bases
  • A conductivity probe for the measure of local void fraction in two-phase flowA conductivity probe for the measure of local void fraction in two-phase flow
  • A continuous level indicator for a liquid metal systemA continuous level indicator for a liquid metal system
  • A discussion of definitions, models, and interpretations employed in the measurement of diffusion lengthsA discussion of definitions, models, and interpretations employed in the measurement of diffusion lengths
  • A discussion of scintillation counting and evaluation of a single channel analyzer using a modified 204-B linear amplifierA discussion of scintillation counting and evaluation of a single channel analyzer using a modified 204-B linear amplifier
  • A discussion of the problems involved in the defection [sic] of fuel element leaks in a sodium cooled reactorA discussion of the problems involved in the defection [sic] of fuel element leaks in a sodium cooled reactor
  • A fault tree analysis of the Midland Nuclear Power Plant dc power systemA fault tree analysis of the Midland Nuclear Power Plant dc power system
  • A feasibility study of the dual use of a nuclear reactor for rocket propulsion and electric power generation on a manned Mars missionA feasibility study of the dual use of a nuclear reactor for rocket propulsion and electric power generation on a manned Mars mission