This dissertation develops a simulation tool capable of optimizing advanced nuclear reactors considering the multiobjective nature of their design. An Enhanced Equilibrium Cycle (EEC) method based on the classic equilibrium method is developed to evaluate the response of the equilibrium cycle to changes in the core design. Advances are made in the consideration of burnup-dependent cross sections and dynamic fuel performance (fission gas release, fuel growth, and bond squeeze-out) to allow accuracy in high-burnup reactors such as the Traveling Wave Reactor. EEC is accelerated for design changes near a reference state through a new modal expansion perturbation method that expands arbitrary flux perturbations on a basis of lambda-eigenmodes. A...
Accurate, high-resolution full core simulations of prismatic high temperature reactors for burnup an...
The Advanced Multi-Physics (AMP) Nuclear Fuel Performance code (AMPFuel) is focused on predicting th...
Monte Carlo codes are powerful and accurate tools for reactor core calculations. For coupled core-ev...
The optimal axial loading strategy of burnable poison in pressurized water reactors is investigated ...
The nuclear industry must address the issues faced by the current new-built plants in the west- ern ...
The material composition of nuclear fuel changes constantly due to nuclides transforming to other nu...
This research focuses on developing a new approach to studying the nuclear fuel cycle: instead of e...
Motivated by the increased importance of high-fidelity modeling capabilities that can improve the ec...
This dissertation presents novel realizations in balancing the economical and environmental constrai...
The problem studied is the finding of the optimum fuel velocityduring the approach to equilibrium fo...
Fuel performance codes are an essential tool for ensuring the safe and economic opera-tion of nuclea...
The Versatile Test Reactor (VTR) is expected to operate in a persistent non-equilibrium state due to...
Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering...
Nuclear in-core fuel management involves all the physical aspects which allow optimal operation of t...
textNuclear fuel cycles (NFC) are the collection of interconnected processes which generate electric...
Accurate, high-resolution full core simulations of prismatic high temperature reactors for burnup an...
The Advanced Multi-Physics (AMP) Nuclear Fuel Performance code (AMPFuel) is focused on predicting th...
Monte Carlo codes are powerful and accurate tools for reactor core calculations. For coupled core-ev...
The optimal axial loading strategy of burnable poison in pressurized water reactors is investigated ...
The nuclear industry must address the issues faced by the current new-built plants in the west- ern ...
The material composition of nuclear fuel changes constantly due to nuclides transforming to other nu...
This research focuses on developing a new approach to studying the nuclear fuel cycle: instead of e...
Motivated by the increased importance of high-fidelity modeling capabilities that can improve the ec...
This dissertation presents novel realizations in balancing the economical and environmental constrai...
The problem studied is the finding of the optimum fuel velocityduring the approach to equilibrium fo...
Fuel performance codes are an essential tool for ensuring the safe and economic opera-tion of nuclea...
The Versatile Test Reactor (VTR) is expected to operate in a persistent non-equilibrium state due to...
Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering...
Nuclear in-core fuel management involves all the physical aspects which allow optimal operation of t...
textNuclear fuel cycles (NFC) are the collection of interconnected processes which generate electric...
Accurate, high-resolution full core simulations of prismatic high temperature reactors for burnup an...
The Advanced Multi-Physics (AMP) Nuclear Fuel Performance code (AMPFuel) is focused on predicting th...
Monte Carlo codes are powerful and accurate tools for reactor core calculations. For coupled core-ev...