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Boiling heat transfer for high velocity flow of highly subcooled water
([Cambridge, Mass. : Dept. of] Nuclear Engineering, Massachusetts Institute of Technology, [1999], 1999)
Data analysis : operating crew characteristics and interactions during steam generator tube rupture simulation
(Cambridge, MA : Nuclear Engineering Dept., Massachusetts Institute of Technology, 1990, 1990)
This report provides an analysis of the data collected during a one-month visit to a 2-unit, non-U.S. PWR. The data consist of results from interviews (largely with plant operators and former shift engineers) and from ...
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 ...
Geometrical effects on axial & azimuthal variations of heat flux to coolant in asymmetrically heated channels
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1998], 1998)
This report summarizes analyses of the effects of heat conduction in a copper block on the heat flux to a coolant flowing axially in the block. Heat is assumed to be added through one side of the block corresponding to ...
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 ...
The Chernobyl accident revisited : source term analysis and reconstruction of events during the active phase
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, 1994, 1994)
Review of applicable U.S. Department of Energy and U.S. Nuclear Regulatory Commission activities : Project task 1
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, [1999], 1999)
Choice of discount rate for cost levelization
(Cambridge, Mass. : [Dept. of] Nuclear Engineering, Massachusetts Institute of Technology, [1991], 1991)
Risk impact of maintenance program changes
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1992], 1992)
This study quantifies the change in one measure of plant risk, the frequency of loss of long-term decay heat removal, due to changes in maintenance at the James A. Fitzpatrick (JAF) plant. Quantification is accomplished ...
Uncertainty evaluations for MITR-3 applications : final report for MITNE-305
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, 1994, 1994)