Abstract
Neutron and gamma dose rate calculations were carried out around horizontal beam tube no. 5 at the Jožef Stefan Institute (JSI) TRIGA Mark II research reactor. Results were compared to the experimental measurements in order to verify the computation model. In addition, another set of calculations and measurements was carried out, where an additional shield made out of concrete and paraffin was installed. With that configuration, we were able to study neutron and gamma scattering.
Highlights
In this article, a major step towards calculating dose rates using the Monte Carlo particle transport code Monte Carlo N-Particle (MCNP) [1] in reactor hall of Jožef Stefan Institute (JSI) TRIGA reactor is presented
A major step towards calculating dose rates using the Monte Carlo particle transport code MCNP [1] in reactor hall of JSI TRIGA reactor is presented
Dose rates in the reactor hall around beam tube no. 5 were calculated for the first time
Summary
A major step towards calculating dose rates using the Monte Carlo particle transport code MCNP [1] in reactor hall of JSI TRIGA reactor is presented. Monte Carlo simulations were used to calculate various parameters in or around JSI TRIGA core [2][3]. Monte Carlo N-Particle (MCNP) is a program package used to simulate transport of neutrons, photons (gamma rays), electrons etc. In this case, it was used to simulate neutrons and prompt gamma rays emitted from an operating reactor. The Monte Carlo method is used to simulate a great number of particles in a desired computer model describing the geometry of the problem including material composition. All nuclear data is at room temperature as reactor was operated at low power)
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