Search
Now showing items 1-6 of 6
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)
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 ...
Transient response of a single heated channel
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, 1984, 1984)
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. ...
Thermal hydraulics of core/concrete interaction of severe LWR accidents
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, 1987, 1987)