Browsing by Advisor/Supervisor
Now showing items 1-14 of 14
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Application of the analytic hierarchy process in selecting medium-term storage options for spent nuclear fuel in South Africa
(North-West University (South Africa), 2021)South Africa is one of the countries using nuclear power and has prospects to expand its use in the near future. The management of spent nuclear fuel (SNF) from nuclear power plants has become a major issue internationally, ... -
Assessing the effect of using supercells instead of lattice blocks on multigroup cross sections of the MHTGR-350 reactor
(North-West University (South Africa), 2020)Uncertainty and sensitivity analysis methods are essential in nuclear reactor design and safety. These methods can be used to predict the probability distributions in output parameters, treat discreet events and handle ... -
A comparative study of the thermo-hydraulics of the SNUF test facility core using FLOWNEX and RELAP5
(North-West University (South Africa)., 2022)In the current energy mix, South Africa sources its energy from coal power, nuclear power, natural gas, hydro power, and various renewable energy sources. From the Integrated Resource Plan released by the Department of ... -
Consistent multi-scale uncertainty quantification methodology for multi-physics modelling of prismatic HTGRs
(North-West University (South Africa), 2020)As one of the Generation-IV advanced reactor types, High Temperature Gas-Cooled Reactors (HTGRs) can provide high-quality heat to industrial processes, in addition to saleable and inherently safe power operation. In the ... -
Criticality study of a spent fuel pool using SCALE 6.2.3 and MCNP6.2
(North-West University (South Africa)., 2022)The North-West University (NWU) through the Reactor Analysis group in UETS plans to conduct research on the spent fuel pool using capabilities of the in-house code, North-West University Reactor Code Suite (NWURCS). Due ... -
Developing a fresh core neutronic model at 300K for a VVER-1000 reactor type using MCNP6
(North-West University (South Africa) , Potchefstroom Campus, 2016)A steady state neutronics model for a fresh core Voda Voda Energo Reaktor (VVER)-1000 reactor type is developed using an internationally recognised code, Monte Carlo N-Particle, version 6 (MCNP6). This research study is ... -
Developing a full core model of the North Anna Reactor using SCALE 6.2.3, NESTLE and MCNP 6.2
(North-West University (South Africa), 2022)This study presents the development of the modelling for a T-NEWT/NESTLE* lattice-to-nodal diffusion calculation. The reactor selected for this study is the North-Anna (NA) Unit 1 Pressurized Water Reactor (PWR) of the ... -
The impact of homogenized cross-section correction mechanisms in OSCAR-4 as applied to SAFARI-1 research reactor
(North-West University, 2019)The nodal solver OSCAR-4 reactor analysis system contains a series of approximations (nonlinear extensions) which aim to correct the full-core nodal calculation (mostly via corrections to the homogenised cross-sections) ... -
Initial implementation of the neutronics codes DRAGON and DONJON at the North-West University
(North-West University (South Africa), 2020)The neutronics research group at the North West University plans to use open source neutronics in some of the future research that will be conducted by the group. The open source neutronics codes DRAGON and DONJON were ... -
Neutronic analysis of selected fuel assemblies of the MIT BEAVRS benchmark using HEADE collision probability code
(North-West University (South Africa), 2019)Neutronic models for fresh core fuel assemblies of the MIT BEAVRS benchmark are developed using the HEADE collision probability code which is a module of the OSCAR-4 code used for research reactor calculations. This research ... -
A neutronic model of the PMR200 prismatic modular reactor using MCNP5
(North-West University (South Africa) , Potchefstroom Campus, 2016)The PMR200 reactor is a prismatic modular High Temperature Reactor. The High Temperature Reactor is a near term Generation IV reactor with the capability of producing electricity, and its high outlet temperature ... -
Quantifying uncertainties of aspects of the neutronics modelling of the Kozloduy-6 system using SCALE 6.2.1
(North-West University (South Africa), 2019)This work is based on the benchmark for Uncertainty Analysis in Modelling (UAM) of light water reactors compiled by the Nuclear Energy Agency within the Organisation for Economic Cooperation and Development (OECD/NEA). The ... -
Radiation dose and radionuclide inventory characterization following a hypothetical nuclear criticality accident at a uranium processing facility
(North-West University (South Africa), 2021)This study focused on a hypothetical nuclear criticality excursion in a Plutonium Uranium Reduction EXtraction (PUREX) processing facility for the recovery of non-irradiated enriched uranium, which are present in scrap ... -
Uncertainty and sensitivity analysis of aspects of the neutronics of a prismatic block-type HTGR
(2019)The International Atomic Energy Agency (IAEA) Coordinated Research Project (CRP) on High Temperature Gas-cooled Reactors (HTGR) Uncertainty Analysis in Modelling (UAM) has been established aiming to study uncertainty ...
