Abstract
A model of the FiR 1 Triga Mk-II reactor has been previously generated for the Serpent Monte Carlo reactor physics and burnup calculation code. In the current article, this model is validated by comparing the predicted reaction rates of nickel and manganese at 9 different positions in the reactor to measurements. In addition, track-length estimators are implemented in Serpent 2.1.18 to increase its performance in dosimetry calculations. The usage of the track-length estimators is found to decrease the reaction rate calculation times by a factor of 7-8 compared to the standard estimator type in Serpent, the collision estimators. The differences in the reaction rates between the calculation and the measurement are below 20%.
Highlights
A model of the FiR 1 Triga Mk-II reactor has been previously developed at VTT for the Serpent Monte Carlo reactor physics code [1, 2]
The current study has two primary functions: First, it validates the FiR 1 Serpent model against experimental data and, second, it familiarizes a new expert with the field of reactor dosimetry by providing hand-on experience on the tools and practices of neutron dosimetry
The Serpent model of the Triga Mk-II research reactor was validated by measuring the nickel and manganese reaction rates at 9 different positions within the reactor and by comparing the results to estimations of the model
Summary
A model of the FiR 1 Triga Mk-II reactor has been previously developed at VTT for the Serpent Monte Carlo reactor physics code [1, 2]. The model has been used to calculate the rod-wise nuclide inventories and burnups. The calculation model has only been validated rather coarsely by checking that the multiplication factor of the system remains within reasonable limits throughout the operational history from 1962 to present and, by comparing the inventories to ORIGEN calculations [3]. As the current reactor physical model involves numerous simplifications and possibly coarse errors, it would be beneficial to proceed with the validation of the model by comparing its predictions to other measurable data. The current study has two primary functions: First, it validates the FiR 1 Serpent model against experimental data and, second, it familiarizes a new expert with the field of reactor dosimetry by providing hand-on experience on the tools and practices of neutron dosimetry
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