A Comparison of Some Analytical Models with Experiment for the University of Maryland Reactor
A Comparison of Some Analytical Models with Experiment for the University of Maryland Reactor
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Date
1968
Authors
Ross, Malcolm Fred Jr
Advisor
Duffey, Dick
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Abstract
It is often desirable in the operation of a research
reactor to make adjustments in the nuclear core configuration.
These adjustments may occur for a variety of
reasons, such as the rearrangement of fuel to perform a
particular experiment. It is beneficial to the reactor
operator and experimenter to have an adequate analytical
model with which to predict the changes in nuclear characteristics
which occur with core rearrangement.
Several analytical models have been investigated
and compared with experimental results for the semipermanent,
or normal, core configuration for the University
of Maryland Reactor. These models were selected because,
while somewhat time consuming with respect to the use of
computers, the computer time utilized is much less than
needed by more complex methods. At the same time, the
methods used tend to minimize the large inherent error
associated with simple hand calculations .
The methods used consist of a two-dimensional few
group diffusion theory coupled with several cross section
models from which macroscopic cross sections were obtained. The cross section models used for the above thermal
energy groups were the volume integrated P-1 method
and the Fourier transform B-1 method. Thermal energy
group cross sections we reobtained using the Wigner-Wilkins
model and the Maxwell-Boltzmann model.
The volume integrated P-1 model and the Wigner-Wilkins
model coupled with the two-dimensional group
diffusion method were found to give the best agreement
with experiment for the semi-permanent core configuration.
This model was then tested over a range of
experiments. The conclusion of this analysis was
that the model was capable of predicting, with reasonable
accuracy, the changes in core reactivity with
core rearrangement.