In the last ten years, the use of gamma-ray spectrometry for geological mapping and mineral exploration has shown considerable growth. With this growth, standardized procedures have been developed for the calibration and processing of the airborne measurements so that they will be independent of survey parameters. This paper describes some of the new developments to convert airborne data to gro...

A study was performed comparing the performance of UO2 and (Th,U-233)O2 fuel in small long-life PWR. The neutronic calculation carried out by PIJ module SRAC2006 done to a cell 10 years operation. conducted varying enrichment U-235 U-233 for 1% - 20% also volume fraction 40%, 45%, 50%, 55%, 60%. observed needed each type gain criticality years, infinite multiplication factor (k-inf) value, conv...

Current efforts to develop high-fidelity multi-physics tools for research reactors with IRT-4M fuel leads the involvement of Monte-Carlo transport and subchannel thermo-hydraulic codes in process safety assessment. based neutronic are often used as a reference tool suitable prediction detailed power distribution. This paper proposes method point-wise reconstruction on Radial Basis Function (RBF...

Calculations of sensitivities of future experiments are a necessary ingredient in experimental high energy physics. Especially in the context of measurements of the neutrino oscillation parameters extensive studies are performed to arrive at the optimal configuration. In this note we clarify the definition of sensitivity as often applied in these studies. In addition we examine two of the most ...

Novel codes allow the prediction of parameters with increased resolution, in comparison to conventional approach, sometimes using meshing smaller than size fuel pin. Optimally, complex geometric structures, like ones included VVER core e.g. corner stiffeners, would be modeled explicitly by novel neutronic codes. In this paper, performance deterministic neutron transport code nTF is studied for ...

Thorium, in this case, 232Th has a higher thermal neutron capture cross-section than 238U, which means that more fertile isotopes can be transmuted and could lead to fissile isotope 233U. In addition, 233U good performance the spectrum. Theoretically, nuclear reactor using thorium fuel also last longer one uranium fuel. The use of TRISO duplex is predicted produce better neutronic behavior pebb...