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THERMIT-2 : a two-fluid model for light water reactor subchannel transient analysis
(Cambridge, Mass. : Massachusetts Institute of Technology, Energy Laboratory, 1981, 1981)
Interfacial exchange relations for two-fluid vapor-liquid flow : a simplified regime map approach
([Cambridge, Mass.] : Massachusetts Institute of Technology, Energy Laboratory, 1981, 1981)
A simplified approach is described for selection of the constitutive relations for the inter-phase exchange terms in the two-fluid code, THERMIT. The approach used distinguishes between pre-CHF and post-CHF conditions. ...
The effect of virtual mass on the characteristics and the numerical stability in two-phase flow
([Cambridge, Mass.] : Massachusetts Institute of Technology, Energy Laboratory, 1981, 1981)
It is known that the typical six equation two-fluid model of the two-phase flow possesses complex characteristics, exhibits unbounded instabilities in the short-wavelength limit and constitutes an ill-posed initial value ...
An investigation of the physical and numerical foundations of two-fluid representation of sodium boiling with applications to LMFBR experiments
(Cambridge, Mass. : Massachusetts Institute of Technology, Energy Laboratory, 1983, 1983)
This work involves the development of physical models for the constitutive relations of a two-fuid, three-dimensional sodium boiling code, THERMIT-6S. The code is equipped with a fluid conduction model, a fuel pin model, ...
Development of models for the two-dimensional, two-fluid code for sodium boiling NATOF-2D
([Cambridge, Mass.] : Massachusetts Institute of Technology, Energy Laboratory, 1981, 1981)
Several features were incorporated into NATOF-2D, a twodimensional, two fluid code developed at M.I.T. for the purpose of analysis of sodium boiling transients under LMFBR conditions. They include improved interfacial mass, ...
TITAN code development for application to a PWR steam line break accident : final report 1983-1984
(Cambridge, Mass. : Energy Laboratory and Dept. of Nuclear Engineering, Massachusetts Institute of Technology, 1984, 1984)
Modification of the TITAN computer code which enables it to be applied to a PWR steam line break accident has been accomplished. The code now has the capability of simulating an asymmetric inlet coolant temperature transient ...
TITAN : an advanced three dimensional coupled neutronicthermal-hydraulics code for light water nuclear reactor core analysis
(Cambridge, Mass. : Massachusetts Institute of Technology, Energy Laboratory and Department of Nuclear Engineering, 1984, 1984)
The accurate analysis of nuclear reactor transients frequently requires that neutronics, thermal-hydraulics and feedback be included. A number of coupled neutronics/thermal-hydraulics codes have been developed for this ...
User's guide for THERMIT-2 : a version of THERMIT for both core-wide and subchannel analysis of light water reactors
([Cambridge, Mass.] : Massachusetts Institute of Technology, Energy Laboratory, 1981, 1981)
This report provides the THERMIT-2 user with programming and input information. THERMIT-2 is the most recent version of THERMIT. This new version contains all of the features and options of the original version of THERMIT ...
Development of a three-dimensional two-fluid code with transient neutronic feedback for LWR applications
(Cambridge, Mass. : Massachusetts Institute of Technology, Energy Laboratory, 1981, 1981)
The development of a three-dimensional coupled neutronics/thermalhydraulics code for LWR safety analysis has been initiated. The transient neutronics code QUANDRY has been joined to the two-fluid thermal-hydraulics code ...
Development and testing of three dimensional, two-fluid code THERMIT for LWR core and subchannel applications
(MIT Energy Laboratory, 1979-12)