Nuclear Science and Engineering / Volume 82 / Number 1 / September 1982 / Pages 19-33
Technical Paper / dx.doi.org/10.13182/NSE82-A19025
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Analytical techniques were developed to analyze pulsed neutron activation measuements in large pipes leading to a determination of the fluid velocity in the pipe. Neutron and gamma-ray Monte Carlo transport calculations were carried out at the neutron tagging and gamma-ray detector positions, for the piping sizes typical of the loss-of-fluid test (LOFT) experiment. Dispersion models were developed, to describe the transport and mixing of the irradiated fluid from the source to the detector location, and the L3-7 LOFT small break neutron activation test data were analyzed. The values of the fluid transport velocity obtained by a phenomenological model based on finite difference equations agree with those found from experiment.