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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)
Availability of the THERMIT thermal hydraulic reactor computer codes through M.I.T.
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1981], 1981)
Three of the THERMIT thermal hydraulic reactor computer codes are available through the Department of Nuclear Engineering at MIT. The three available codes are THERMIT-2, for LWR subchannel analysis, THIOD, for BWR analysis ...
Modeling of corium/concrete interaction
([Cambridge, Mass.] : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1985, 1985)
Aspects of environmental and safety analysis of fusion reactors
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, [1977], 1977)
This report summarizes the progress made between October 1976 and September 1977 in studies of some environmental and safety considerations in fusion reactor plants. A methodology to assess the admissible occurrence rate ...
Reactor physics project final report
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1970], 1970)
This is the final report in an experimental and theoretical program to develop and apply single- and few-element methods for the determination of reactor lattice parameters. The period covered by the report is January 1, ...
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 ...
Application of probabilistic consequence analysis to the assessment of potential radiological hazards of fusion reactors
(Cambridge. Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1978], 1978)
A methodology has been developed to provide system reliability criteria based on an assessment of the potential radiological hazards associated with a fusion reactor design and on hazard constraints which prevent fusion ...
Transient response of a single heated channel
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, 1984, 1984)
Theoretical studies on some aspects of molten fuel-coolant thermal interaction
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1973], 1973)
Rapid generation of high pressures and mechanical work may result when thermal energy is transferred from the hot molten nuclear fuel to the coolant in an LMFBR accident. Such energetic thermal interactions are facilitated ...
An Introduction to the THERMIT thermal hydraulic reactor computer codes at M.I.T.
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1981], 1981)
The THERMIT thermal hydraulic reactor computer codes developed at MIT are described. The codes include THERMIT-2, THIOD, NATOF-2D, THERMIT-3, THERMIT-2D-PLENUM, THERFLIBE, THERLIT, THERMIT (sodium) and THERMIT-SIEX. ...