Search
Now showing items 1-2 of 2
Development and testing of three dimensional, two-fluid code THERMIT for LWR core and subchannel applications
(MIT Energy Laboratory, 1979-12)
A condensed review of nuclear reactor thermal-hydraulic computer codes for two-phase flow analysis
(MIT Energy Laboratory, 1980-02)
A review is made of the computer codes developed in the
U.S. for thermal-hydraulic analysis of nuclear reactors. The
intention of this review is to compare these codes on the
basis of their numerical method and ...