Browsing by Author "Nichita, Eleodor"
Now showing items 1-8 of 8
-
Development of a 37-element fuel bundle for the production of molybdenum-99 in CANDU power reactors.
Haroon, Jawad (2014-08-01)In this study, the potential use of CANDU power reactors for the production of Mo-99 is assessed. Five different modifications of a 37-element fuel bundle that could be used for the production of Mo-99 in existing CANDU ... -
Development of a point-kinetics simulator for molten-salt reactors
Mazher, Momal (2022-08-01)Molten-salt-fueled reactors (MSRs) are nuclear fission reactors that use a mixture of fissile material and molten fluoride salts as both fuel and primary coolant. Such reactors, which can operate at low pressure and high ... -
Investigation of a SPH-based sub-cell homogenization for PHWR using a multi-cell model
Ferguson, Thomas (2018-06-01)Superhomogenization (SPH) has gained interest in the industry as a possible method to overcome the inherent limitations of standard homogenization (SH) for full nuclearreactor-core neutronics calculations because its ... -
Investigation of sub-cell homogenization for PHWR lattice cells using superhomogenization factors
Mohapatra, Subhramanyu (2016-12-01)To avoid the computational effort associated with full-core neutron transport calculations, full-core neutronics calculations for Pressurized Heavy-Water Reactors (PHWRs) are usually performed in diffusion theory using an ... -
Leakage-corrected discontinuity factors for a second-generation Th-Pu pressure-tube SCWR.
Carisse, Katarzyna (2014-08-01)The neutron flux throughout a reactor core should be calculated, ideally, by solving the neutron transport equation for a highly detailed geometric model of the core. Since this is computationally impractical, approximate ... -
Microreactor for remote Canadian communities
Crowell, Jordan (2022-11-01)Remote Canadian communities rely on diesel generators for their electricity needs. Providing such generators with fuel year-round presents challenges because of inclement weather and long transportation distances involved. ... -
Moderator displacers for reducing coolant void reactivity in CANDU reactors: a neutronics scoping study.
Farkas, Robert (2014-08-01)When the coolant is voided in a CANDU lattice, the net reactivity change is positive, due primarily to the fact that the coolant and moderator are separated and the coolant volume is much smaller than the moderator volume. ... -
Simulation of dynamic response of Self-Powered-Inconel-Neutron-Detector lead cables using a semi-empirical model
Yu, Jin (2013-11-01)The work presented here was devoted to the modelling and simulation of the dynamic response of lead cables of Inconel self-powered neutron detectors in a CANDUpower reactor. The main goal was to develop a semi-empirical ...