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Monte Carlo Modeling of the Portuguese Research Reactor Core and Comparison with Experimental Measurements

Volume 143 · Number 3 · September 2003 · Pages 358-363
Technical Note · Fission Reactors

Ana C. Fernandes, Isabel C. Gonçalves, Nuno P. Barradas, António J. Ramalho

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The Monte Carlo code MCNP-4C was used to calculate the effective multiplication coefficient of a core configuration of the Portuguese Research Reactor (RPI) and the neutron fluxes in the core and in the reflector region.
A comparison of the results obtained with MCNP and with the deterministic codes WIMSD-5 and CITATION was made. Consistent deviations of 2% for the effective multiplication constant and 8 to 28% for the neutron flux, depending on the energy range, were observed.
Thermal, epithermal, and fast neutron flux measurements were performed using activation detectors. The calculations agree with experimental values within <15%; therefore, the Monte Carlo results can be used to predict the neutron field in other locations and irradiation facilities of the RPI.
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