Methods of implementing uncertainty within nuclear reactor modelling have traditionally been achieved via worst case scenario uncertainty quantification. This article investigates how this practice can be expanded to provide data on the driving factors behind the temperatures experienced during accident conditions via a global sensitivity analysis. The second part of the article investigates how a stochastic optimization technique can be included within the design process to provide the most cost-effective core geometry which meets the temperature constraints of the fuel and the reactor pressure vessel. The third study investigates the impact of how uncertainty reduction can be used in combination with the stochastic optimization technique ...
Nuclear thermal propulsion (NTP) designs include large margins for manufacturing, thermal, and neutr...
The Design of Reactor Pressure Vessel (RPV) should be that the height of pressure vessel is up to 16...
International audienceIn the past ten years, the Working Group for the Analysis and Management of ac...
Methods of implementing uncertainty within nuclear reactor modelling have traditionally been achieve...
Abstract Methods of implementing uncertainty within nuclear reactor modelling have tr...
The High Temperature Reactor (HTR) is one of the six Generation IV advanced reactor designs. HTRs ha...
MIng (Nuclear Engineering), North-West University, Potchefstroom Campus, 2014This study was based on...
With steady increase in energy consumption, the vulnerability of the fossil fuel supply, and environ...
The continued development of High Temperature Gas Cooled Reactors (HTGRs) requires verification of d...
Sophisticate computational tools exist in nuclear thermal-hydraulics; however, approximations and hy...
As pressure grows on developed nations to move away from fossil fuel-based energy sources, so does t...
The structures associated with the nuclear steam supply system (NSSS) of a pressurized water reactor...
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2012...
The structures associated with the nuclear steam supply system (NSSS) of a pressurized water reactor...
Thesis (M.Ing. (Mechanical Engineering))--North-West University, Potchefstroom Campus, 2007.The worl...
Nuclear thermal propulsion (NTP) designs include large margins for manufacturing, thermal, and neutr...
The Design of Reactor Pressure Vessel (RPV) should be that the height of pressure vessel is up to 16...
International audienceIn the past ten years, the Working Group for the Analysis and Management of ac...
Methods of implementing uncertainty within nuclear reactor modelling have traditionally been achieve...
Abstract Methods of implementing uncertainty within nuclear reactor modelling have tr...
The High Temperature Reactor (HTR) is one of the six Generation IV advanced reactor designs. HTRs ha...
MIng (Nuclear Engineering), North-West University, Potchefstroom Campus, 2014This study was based on...
With steady increase in energy consumption, the vulnerability of the fossil fuel supply, and environ...
The continued development of High Temperature Gas Cooled Reactors (HTGRs) requires verification of d...
Sophisticate computational tools exist in nuclear thermal-hydraulics; however, approximations and hy...
As pressure grows on developed nations to move away from fossil fuel-based energy sources, so does t...
The structures associated with the nuclear steam supply system (NSSS) of a pressurized water reactor...
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2012...
The structures associated with the nuclear steam supply system (NSSS) of a pressurized water reactor...
Thesis (M.Ing. (Mechanical Engineering))--North-West University, Potchefstroom Campus, 2007.The worl...
Nuclear thermal propulsion (NTP) designs include large margins for manufacturing, thermal, and neutr...
The Design of Reactor Pressure Vessel (RPV) should be that the height of pressure vessel is up to 16...
International audienceIn the past ten years, the Working Group for the Analysis and Management of ac...