Browsing Dept. of Nuclear Engineering Technical Reports by Title
Now showing items 144-163 of 262
-
Laminar film condensation in zero gravity
(Cambridge, Mass. Nuclear Engineering Dept., Massachusetts Institute of Technology, [1960], 1960) -
LMFBR Blanket Physics Project progress report no. 1
(Cambridge, Mass., Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1970], 1970) -
LMFBR Blanket Physics Project progress report no. 2
(Cambridge, Mass., Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1971], 1971) -
LMFBR Blanket Physics Project progress report no. 3
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1972], 1972) -
LMFBR Blanket Physics Project progress report no. 4
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1973], 1973) -
LMFBR Blanket Physics Project progress report no. 5
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1974], 1974) -
LMFBR Blanket Physics Project progress report no. 7
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1970], 1970) -
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 ...