Browsing Department of Nuclear Engineering by Title
Now showing items 92-111 of 262
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An experiment to simulate the heat transfer properties of a dry, horizontal spent nuclear fuel assembly
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1991], 1991)Nuclear power reactors generate highly radioactive spent fuel assemblies. Initially, the spent fuel assemblies are stored for a period of several years in an on-site storage facility to allow the radioactivity levels of ... -
An experimental investigation of acoustic cavitation as a fragmentation mechanism of molten tin droplets in water
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, [1974], 1974)A series of experiments were performed where single molten tin droplets of known size, shape and temperature were dropped from a low height into a pool of distilled water. The pressure waves emanating from the hot droplets ... -
Experimental investigation of the thermal-hydraulics of gas jet expansion In a two-dimensional liquid pool
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, [1978], 1978)Gas jet blowdown in a two-dimensional liquid pool has been experimentally investigated. Two sets of experiments were performed: a set of hydrodynamic experiments, where a non-condensible gas is injected into a subcooled ... -
Fast neutron shielding studies
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1969?], 1969?) -
Final report on improved uranium utilization in PWRs
(Cambridge, Mass. : Massachusetts Institute of Technology, Energy Laboratory, 1982, 1982)This is the final summary progress report on a research program carried out within the MIT Energy Laboratory/Nuclear Engineering Department under the US Department of Energy's program to increase the effectiveness of uranium ... -
Final report, U.S. Bureau of Mines Contract number H0180895
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1971, 1971) -
Finite difference techniques for the solution of the reactor kinetics equations
(Cambridge, Mass. Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1969, 1969) -
The finite element method applied to neutron diffusion problems
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1973, 1973) -
The finite element method for neutron diffusion problems in hexagonal geometry
(Cambridge, [Mass.] : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1975, 1975) -
Finite element methods for space-time reactor analysis
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1971, 1971) -
Finite element synthesis method
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1975, 1975) -
First annual report : organic moderator-coolant in-pile irradiation loop for the MIT nuclear reactor : October 1, 1958 to October 1, 1959
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, 1961, 1961) -
FRANTIC 5 (a version of FRANTIC II) : a computer code for evaluating system aging effect
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, [1986], 1986)The FRANTIC 5 code is a modification of the FRANTIC II code for time dependent unavailability analysis. FRANTIC 5 is specially adapted for modeling the aging effects on system and component performance. The FRANTIC 5 code ... -
Friction factor and heat transfer correlation for irradiated organic coolants
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, [1965], 1965) -
Fuel cycle analysis in a thorium fueled reactor using bidirectional fuel movement
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1964, 1964) -
Fuel cycle analysis in a thorium fueled reactor using bidirectional fuel movement : correction to report MIT-2073-1, MITNE-51
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, [1965], 1965)This report corrects an error discovered in the code used in the study "Fuel Cycle Analysis in a Thorium Fueled Reactor Using Bidirectional Fuel Movement," MIT-2073-1, MITNE-51. The results of the correction show considerable ... -
Fuel cycle code, "FUELMOVE III"
([Cambridge, Mass.] Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1963, 1963)Further modifications to the fuel cycle code FUELMOVE are described which were made in an attempt to obtain results for reflected reactors operated under batch, outin, and bidirectional fueling schemes. Numerical methods ... -
The fuel cycle economics of improved uranium utilization in light water reactors
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering and Energy Laboratory ; Springfield, Va. : Available from National Technical Information Service, 1979, 1979) -
Fuel cycles in nuclear reactors
([Cambridge, Mass.] : Massachusetts Institute of Technology, Nuclear Engineering Dept., 1959, 1959) -
GAKIN II : a one-dimensional multigroup diffusion theory reactor kinetics code
([Cambridge, Mass. Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1973], 1973)