Since 2005 the nodal diffusion based code system, OSCAR-3, was used for reactor support calculations of operational cycles High Flux Reactor in Petten, The Netherlands. OSCAR uses a two-step deterministic calculation, which homogenized cross sections are generated lattice environments using neutron transport simulations, and then passed to core simulator model full reactor. Limitations OSCAR-3 ...

background: decrease of economically accessible uranium resources motivates consideration of breeding of fertile elements such as thorium. material and method: thorium oxide fuel burn up calculation of a simulated research reactor cooled heavy water has been proposed in the present work using mcnpx 2.6 code. two 233u and 235u isotopes have been used as fissile element of thorium oxide fuel. 135...

Anomalous results from a variety of neutrino experiments, astrophysical observations, and cosmology suggest the possible existence of sterile neutrinos. Most recently, a re-analysis of short-baseline reactor neutrino experiments has revealed a discrepancy between observations and the predicted antineutrino flux. While the spectral shape and uncertainties obtained in this work are comparable to ...

The shift towards multi-core architectures has ushered in a new era of shared memory parallelism for scientific applications. This transition has introduced challenges for the nuclear engineering community as it seeks to design high-fidelity full-core reactor physics simulation tools. This paper describes the parallel transport sweep algorithm in the OpenMOC method of characteristics (MOC) neut...

Several concepts of new reactors use graphite. Some them graphite as a moderator, some reflector. There are at least two these graphitetype under development in the Czech Republic. Both An in-core measurement might be impossible to because various reasons, for instance, high temperature or aggressive environment. Therefore, this article focuses on ex-core neutron flux system placed reflector an...

Abstract Stochastic fluctuations of the neutron population within a nuclear reactor are typically prevented by operating core at sufficient power, since deterministic (i.e., exactly predictable) behavior is required automatic safety systems to detect unwanted power excursions. In order characterize conditions which vanish, an experiment was designed and took place in 2017 Rensselaer Polytechnic...

In this paper we study a self-adaptive predictive functional control algorithm as an approach to the control of the temperature in an exothermic atch reactor. The batch reactor is located in a pharmaceutical company in Slovenia and is used in the production of medicines. Due to mixed discrete nd continuous inputs the reactor is considered as a hybrid system. The model of the reactor used for th...