Browsing Department of Nuclear Engineering by Title
Now showing items 171-190 of 262
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Narrow channel turbulence modeling project : final report
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [], ) -
Natural convection in high heat flux tanks at the Hanford Waste Site / [by] Mark van der Helm and Mujid S. Kazimi
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1996], 1996)A study was carried out on the potential for natural convection and the effect of natural convection in a High Heat Flux Tank, Tank 241-C-106, at the Hanford Reservation. To determine the existence of natural convection, ... -
The nature of the high boiler degradation products from irradiated Santowax OMP
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1965, 1965) -
Neutron and gamma-ray spectroscopy and activation analysis : final report
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1966, 1966) -
Neutron capture gamma rays of 75 elements listed in terms of increasing gamma-ray energy
(Cambridge,Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1969, 1969) -
Neutron dosimetry, spectrometry, and neutron activation analysis : final report
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1961, 1961) -
Neutron thermalization at a temperature discontinuity
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1966, 1966) -
Neutronic analysis of a proposed plutonium recycle assembly
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1975], 1975)A method for the neutronic analysis of plutonium recycle assemblies has been developed with emphasis on relative power distribution prediction in the boundary area of vastly different spectral regions. Such regions are ... -
Neutronic sensitivity studies on MEKIN, an accident analysis computer code for nuclear reactors
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1977, 1977) -
A new approach to solving the multimode kinetics equations
([Cambridge, Mass. Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1972], 1972) -
Nondestructive analyses of irradiated MITR fuel by gamma ray spectroscopy
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1965, 1965) -
Nonlinear methods for solving the diffusion equation
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1976], 1976)This thesis is concerned with methods for the transient solution of the neutron diffusion equations in one or two energy groups. Initially, nonlinear methods for solving the static diffusion equations using the finite ... -
Nuclear power plant design innovation for the 1990s : a preliminary assessment
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, 1983, 1983) -
Numerical solution of the two-dimensional time-dependent multigroup equations
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1969, 1969) -
Optimization of material distributions in fast breeder reactors
(Cambridge, Mass. Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1971, 1971) -
Optimization of the axial power shape in pressurized water reactors
(Cambridge, Mass. : Massachusetts Institute of Technology, Energy Laboratory, 1981, 1981)Analytical and numerical methods have been applied to find the optimum axial power profile in a PWR with respect to uranium utilization. The preferred shape was found to have a large central region of uniform power density, ... -
Organic moderator-coolant in-pile irradiation loop for the MIT nuclear reactor
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1961, 1961) -
Physical dependencies in accident sequence analysis
(Cambridge, MA : Nuclear Engineering Dept., Massachusetts Institute of Technology, 1989, 1989) -
PL-MODT and PL-MODMC : two codes for reliability and availability analysis of complex technical systems using the fault tree modularization technique
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, [1978], 1978)The methodology used in the PL-MOD code has been extended to include the time-dependent behavior of the fault tree components. Four classes of components are defined to model time-dependent fault tree leaves. Mathematical ... -
Pressurized water reactor loss-of-coolant accidents by hypothetical vessel rupture
([Cambridge, Mass.] : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1972, 1972)