Browsing Dept. of Nuclear Engineering Technical Reports by Title
Now showing items 1-20 of 262
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The 1994 MIT NED-DOE intern program
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, 1994, 1994) -
An accident probability analysis and design evaluation of the gas-cooled fast breeder reactor demonstration plant
(Cambridge, [Mass.] : Massachusetts Institute of Technology Dept. of Nuclear Engineering, 1976, 1976) -
Activities in nuclear engineering at M.I.T.
([Cambridge, Mass.] : Nuclear Engineering Dept., Massachusetts Institute of Technology, [1989], 2014-09-16) -
Activities in nuclear engineering at M.I.T.
([Cambridge, Mass.] : Nuclear Engineering Dept., Massachusetts Institute of Technology, [1991], 2014-09-16) -
Activities in nuclear engineering at M.I.T.
([Cambridge, Mass.] : Nuclear Engineering Dept., Massachusetts Institute of Technology, [1978], 2014-09-16) -
Activities in nuclear engineering at M.I.T.
([Cambridge, Mass.] : Nuclear Engineering Dept., Massachusetts Institute of Technology, [1981], 2014-09-16) -
Activities in nuclear engineering at M.I.T.
([Cambridge, Mass.] : Nuclear Engineering Dept., Massachusetts Institute of Technology, [1975], 2014-09-16) -
Activities in nuclear engineering at M.I.T.
([Cambridge, Mass.] : Nuclear Engineering Dept., Massachusetts Institute of Technology, [1984], 2014-09-16) -
Activities in nuclear engineering at M.I.T.
([Cambridge, Mass.] : Nuclear Engineering Dept., Massachusetts Institute of Technology, [1985], 2014-09-16) -
Activities in nuclear engineering at M.I.T.
([Cambridge, Mass.] : Nuclear Engineering Dept., Massachusetts Institute of Technology, [1976], 2014-09-16) -
Activities in nuclear engineering at M.I.T.
([Cambridge, Mass.] : Nuclear Engineering Dept., Massachusetts Institute of Technology, [1980], 2014-09-16) -
Activities in nuclear engineering at M.I.T.
([Cambridge, Mass.] : Nuclear Engineering Dept., Massachusetts Institute of Technology, [1987], 2014-09-16) -
Activities in nuclear engineering at M.I.T.
([Cambridge, Mass.] : Nuclear Engineering Dept., Massachusetts Institute of Technology, [1973], 2014-09-16) -
Ammonia distillation for deuterium separation
([Cambridge, Mass.] : Massachusetts Institute of Technology, Nuclear Engineer Dept., 1960, 1960) -
Analysis of conventional and plutonium recycle unit-assemblies for the Yankee (Rowe) PWR
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1971], 1971)An analysis and comparison of Unit Conventional UO2 Fuel-Assemblies and proposed Plutonium Recycle Fuel Assemblies for the Yankee (Rowe) Reactor has been made. The influence of spectral effects, at the watergaps -and ... -
Analysis of design strategies for mitigating the consequences of lithium fire within containment of controlled thermonuclear reactors
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1978, 1978) -
Analysis of forced convection degraded core cooling in light water reactors
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1981, 1981) -
Analysis of mixing data relevant to wire wrapped fuel assembly thermal-hydraulic design
(Cambridge, Mass. : Departments of Mechanical Engineering and Nuclear Engineering, Massachusetts Institute of Technology [1974], 1974)In this report analysis of recent experimental data is presented using the ENERGY code. A comparison of the accuracy of three types of experiments is also presented along with a discussion of uncertainties in utilizing ... -
Analysis of operating data related to power and flow distribution in a PWR
(Cambridge, Mass. Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1974], 1974)The analysis of the effects of the uncertainties associated with temperature and power measurements in the Connecticut Yankee Reactor leads to the evaluation of the uncertainty associated with the effective flow factor. ... -
An analysis of plutonium recycle fuel elements in San Onofre-1
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1974], 1974)A method has been developed to allow independent assessment of the use of plutonium recycle assemblies in operating reactors. This method utilizes Generalized Mixed Number Density (GMND) cross sections (based on Breen's ...
