Development of a method for BWR subchannel analysis
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MIT-EL-79-027-06521124.pdf
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Author(s)
Faya, Artur José Goncalves
Wolf, Lothar
Todreas, Neil E.
Date Issued
November 1979
Publisher
MIT Energy Laboratory
Series/Report no.
MIT-EL
79-027
Abstract
This study deals with the development of a computer pro-
gram for steady-state and transient BWR subchannel analysis.
The conservation equations for the subchannels are obtained
by area-averaging of the two-fluid model conservation equa-
tions and reducing them to the drift-flux model formulation.
The conservation equations are solved by a marching type
technique which limits the code to analysis of operational
transients only. The transfer of mass, momentum and energy
between adjacent subchannels is split into diversion cross-
flow and turbulent mixing components. The transfer of mass
by turbulent mixing is assumed to occur in a volume-for-
volume scheme reflecting experimental observations. The
phenomenon of lateral vapor drift and mixing enhancement with
flow regime are included in the mixing model of the program.
The following experiments are used for the purpose of the
assessment of the code under steady-state conditions:
1) GE Nine-Rod tests with radially uniform and nonuniform
heating
2) Studsvik Nine-rod tests with strong radial power tilt
3) Ispra Sixteen-rod tests with radially uniform heating
Comparison of calculated results with these data shows
that the program is capable of predicting the correct trends
in exit mass velocity and quality distributions.
Description
Originally presented as the author's thesis, Ph.D. in the M.I.T. Dept. of Nuclear Engineering, 1980.
Subjects
Nuclear fuel elements |x Mathematical models.
Nuclear fuel elements |x Computer programs.
Boiling water reactors.
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