Browsing Department of Nuclear Engineering by Title
Now showing items 243-262 of 262
-
Technical specifications for the MIT Research Reactor
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1965], 1965) -
Technical specifications for the MIT Research Reactor
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1967], 1967) -
Theoretical studies on some aspects of molten fuel-coolant thermal interaction
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1973], 1973)Rapid generation of high pressures and mechanical work may result when thermal energy is transferred from the hot molten nuclear fuel to the coolant in an LMFBR accident. Such energetic thermal interactions are facilitated ... -
Theory and use of small subcritical assemblies for the measurement of reactor parameters
(Cambridge, Mass. Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1962, 1962) -
Thermal hydraulics of core/concrete interaction of severe LWR accidents
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, 1987, 1987) -
Thermal neutron capture gamma-ray spectra of the elements
(Cambridge, Mass. : Massachusetts Institute of Technology, 1969, 1969) -
Time integration methods for reactor kinetics
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [], )A technique based on the Padé approximations is applied to the solution of the point kinetics equations. The method consists of treating explicitly the roots of the inhour formula which would make the Padé approximations ... -
A time-dependent, two-phase, thermal hydraulic feedback model for the Nodal code QUANDRY
([Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology], 1980, 1980) -
Transient heat transfer induced pressure fluctuations in the fuel coolant interaction
(Cambridge, Mass. : Massachusetts Institute of Technology. Dept. of Nuclear Engineering, 1973, 1973) -
Transient response of a single heated channel
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, 1984, 1984) -
Uncertainty evaluations for MITR-3 applications : final report for MITNE-305
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, 1994, 1994) -
Uranium from seawater research : final progress report, FY 1982
(Cambridge, Mass. : Massachusetts Institute of Technology, Energy Laboratory, 1982, 1982)During the FY '82 campaign 14 new ion exchange resin formulations, prepared by the Rohm & Haas Company, were tested by MIT at the Woods Hole Oceanographic Institution. The best of these chelating resins was again of the ... -
Use of a moments method for the analysis of flux distributions in subcritical assemblies
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1968], 1968)A moments method has been developed for the analysis of flux distributions in subcritical neutron-multiplying assemblies. The method determines values of the asymptotic axial and radial buckling, and of the extrapolated ... -
Use of a pulsed neutron source to determine nuclear parameters of lattices of partially enriched uranium rods in heavy water
([Cambridge, Mass.] : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1966, 1966) -
The use of burnable poison to improve uranium utilization in PWRs
(Cambridge, Mass. : Massachusetts Institute of Technology, Energy Laboratory, 1982, 1982)A methodology based on the linear reactivity model of core behavior has been developed and employed to evaluate fuel management tactics for improving uranium utilization in Pressurized Water Reactors in a once-through fuel ... -
The Use of experiments on a single fuel element to determine the nuclear parameters of reactor lattices
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1967], 1967)The nuclear parameters of a reactor lattice may be determined by critical experiments on that lattice, by theoretical calculations in which only cross sections are used as input, or by methods which combine theory and ... -
Use of gamma spectroscopy for neutronic analysis of LMFBR Blankets
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [], )It was the purpose of the present investigation to extend and apply Ge(Li) gamma-ray spectroscopy to the study of fast reactor blankets. The focal point for this research was the Blanket Test Facility at the MITR and Blanket ... -
Use of neutron absorbers for the experimental determination of lattice parameters in subcritical assemblies
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1966], 1966) -
Utility system integration and optimization models for nuclear power management
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1973], 1973)A nuclear power management model suitable for nuclear utility systems optimization has been developed for use in multi-reactor fuel management planning over periods of up to ten years. The overall utility planning model ... -
Variational derivation of modal-nodal finite difference equations in spatial reactor physics
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1972], 1972)A class of consistent coarse mesh modal-nodal approximation methods is presented for the solution of the spatial neutron flux in multigroup diffusion theory. The methods are consistent in that they are systematically derived ...