Development of models for the sodium version of the two-phase three dimensional thermal hydraulics code THERMIT
Name
MIT-EL-80-010-06984503.pdf
Size
6.64 MB
Format
Adobe PDF
Checksum (MD5)
458cf5bf2b10d6a1c5bcc38c0c20103b
Author(s)
Wilson, Gregory James
Kazimi, Mujid S.
Date Issued
May 1980
Publisher
MIT Energy Laboratory
Series/Report no.
MIT-EL
80-010
Abstract
Several different models and correlations were developed
and incorporated in the sodium version of THERMIT, a thermal-
hydraulics code written at MIT for the purpose of analyzing
transients under LMFBR conditions. This includes: a mechanism
for the inclusion of radial heat conduction in the sodium coolant
as well as radial heat loss to the structure surrounding the test
section. The fuel rod conduction scheme was modified to allow
for more flexibility in modelling the gas plenum regions and
fuel restructuring. The formulas for mass and momentum exchange
between the liquid and vapor phases were improved. The single
phase and two phase friction factors were replaced by correlations
more appropriate to LMFBR assembly geometry.
The models incorporated in THERMIT were tested by running
the code to simulate the results of the THORS Bundle 6A experiments
performed at Oak Ridge National Laboratory. The results demonstrate
the increased accuracy provided by the inclusion of these effects.
Subjects
Two-phase flow |x Mathematical models
Nuclear fuel elements |x Computer programs
Liquid metal fast breeder reactors
Sodium cooled reactors
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