High resolution measurements with miniature neutron scintillators in the SUR-100 zero power reactor

Three 1-mm3 miniature fiber-coupled scintillators have been used to perform cm-wise resolution measurements of the thermal neutron flux within experimental channels of the SUR-100 facility, a zero power thermal reactor operated by the Institute of Nuclear Technology and Energy Systems at the University of Stuttgart. The detection system is developed at the École Polytechnique Fédérale de Lausanne in collaboration with the Paul Scherrer Institut. Thermal neutrons count rates were measured along the experimental channels I and II, which cross the reactor at the center and tangentially to the core, respectively. The reactor was modelled with the Monte Carlo neutron transport code Serpent-2.1.31. The comparison of experimental and computed reaction rate distributions showed a good agreement within the core region, with discrepancies within 2σ. An unexpected discrepancy, probably caused by a geometric inconsistency in the computational model of the reactor, was observed in the reflector region of the experimental channel I, where a 20% difference (i.e. 8σ) was found between experimental and simulated results. Significant discrepancies, respectively worth 10σ and 15σ, were noticed at distance, in the lead shielding region, for both experimental channels I and II. In addition, reaction rate gradients across the 2.6 cm and 5.4 cm diameters of both channels were measured. A horizontal reaction rate gradient of (9.09 ± 0.20) % was measured within 2.4 cm across the diameter of the experimental channel II, with a difference from computed results of 2%. The absence of a vertical reaction rate gradient inside the experimental channel I was confirmed by measurements.

Certification of a specialized source of gamma radiation spatially combined with modeling reference field of neutron radiation

The results of metrological studies of the field of the experimental channel of the research nuclear reactor OR (experimental base of the NRC “Kurchatov Institute”) with a capacity of 0.1–300 kW are presented. The empirical dependence of the contribution of the absorbed dose of gamma radiation during the raising and lowering reactor power in the total absorbed dose during the irradiation in the reactor and absorbed dose rate from a power reactor OR in the steady state. Based on these results, the absorbed dose and absorbed dose rate of gamma radiation can be pre-calculated. According to metrological studies results, the experimental channel of the reactor OR was certified in terms of the absorbed dose rate of gamma radiation as a specialized source of gamma radiation spatially combined with the modeling reference field of neutrons. The specialized source is designed for calibration of special-purpose measuring instruments and testing for radiation resistance of products operating in conditions of mixed gamma-neutron radiation of nuclear reactors.

Comparative study between turbulence models in curved channels

ABSTRACT This paper presents a comparative study between results obtained in two-dimensional computational simulations performed with three different turbulence models: constant viscosity; Elder Model and k˗Ꜫ Model. The simulations were performed using the software Telemac 2D. These results were compared to data obtained from a study in experimental channel with trapezoidal cross-section and composed of straight stretches and curves. The main objective of this comparison is to explore how turbulence models affect the general behavior of the simulated flow. To support these comparisons, statistical analysis were adopted to quantify the differences between the velocity fields obtained in the simulations and that observed in the experimental channel. The results showed that, despite the theoretical limitations, the use of the simpler turbulence closure model, that is the constant turbulent viscosity, can lead to results as good as or better than those obtained with more sophisticated models.