Browsing Department of Nuclear Engineering by Title
Now showing items 151-170 of 262
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M.I.T. LMFBR Blanket Physics Project : final summary report
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1983], 1983)This is a final summary report on an experimental and analytical program for the investigation of LMFBR blanket characteristics carried out at M.I. T. in the period 1969-1983. During this span of time, work was carried out ... -
Mathematical models for predicting the thermal performance of closed-cycle waste dissipation systems
(Cambridge, [Mass.] : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1976, 1976) -
Measurement of gamma-ray spectra from thermal-neutron capture
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1963, 1963) -
The measurement of reactor parameters in slightly enriched uranium, heavy water moderated miniature lattices
([Cambridge, Mass.] : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1966, 1966) -
Measurement of the ratio of fissions in U²³⁸ to fissions in U²³⁵ using 1.60 mev gamma rays of the fission product La¹⁴⁰
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1963, 1963) -
Measurements of neutron capture in U²³⁸ in lattices of uranium rods in heavy water
(Cambridge, Mass. Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1962, 1962) -
Measurements of reactor parameters in subcritical and critical assemblies : a review
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1962, 1962) -
Measurements of the material bucklings of lattices of natural uranium rods in D₂O
([Cambridge, Mass.] : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1962, 1962) -
Measurements of the spatial and energy distribution of thermal neutrons in uranium, heavy water lattices
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1962], 1962)Intracell activity distributions were measured in three natural uranium, heavy water lattices of 1. 010 inch diameter, aluminum clad rods on triangular spacings of 4. 5 inches, 5. 0 inches, and 5. 75 inches, respectively, ... -
A method for risk analysis of nuclear reactor accidents
(Cambridge : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1978, 1978) -
A method of short-range system analysis for electric utilities containing nuclear plants
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1975, 1975) -
MITR-II start-up report
([Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1977], 1977) -
Modeling control room crews for accident sequence analysis
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1991], 1991)This report describes a systems-based operating crew model designed to simulate the behavior of an nuclear power plant control room crew during an accident scenario. This model can lead to an improved treatment of potential ... -
Modeling of corium/concrete interaction
([Cambridge, Mass.] : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1985, 1985) -
Modeling of fuel-to-steel heat transfer in core disruptive accidents
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, [1980], 1980)A mathematical model for direct-contact boiling heat transfer between immiscible fluids was developed and tested experimentally. The model describes heat transfer from a hot fluid bath to an ensemble of droplets of a cooler ... -
Models and evaluation of human-machine systems
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1993], 1993)The field of human-machine systems and human-machine interfaces is very multidisciplinary. We have to navigate between the knowledge waves brought by several areas of the human learning: cognitive psychology, artificial ... -
Modifications to fuel cycle code "FUELMOVE"
([Cambridge, Mass.] Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1963, 1963) -
A modular approach to fault tree and reliability analysis
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1977, 1977) -
Multi-group diffusion methods
(Cambridge [Mass.] : Massachusetts Institute of Technology, Dept. of Nuclear Engineering. 1962, 1962) -
Multidimensional modeling of the rod drop accident
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, 1976, 1976)