The calculation of macroscopic neutron cross-sections is a fundamental part of the continuous-energy Monte Carlo (MC) neutron transport algorithm. MC simulations of full nuclear reactor cores are computationally expensive, making high-accuracy simulations impractical for most routine reactor analysis tasks because of their long time to solution. Thus, preparation of MC simulation algorithms for next generation supercomputers is extremely important as improvements in computational performance and efficiency will directly translate into improvements in achievable simulation accuracy. Due to the stochastic nature of the MC algorithm, cross-section data tables are accessed in a highly randomized manner, resulting in frequent cache misses and la...
This research presents new code for Monte Carlo N-Particle (MCNP) to achieve an improved time during...
Monte Carlo neutron transport codes are a growing subject of research in nuclear reactor analysis. F...
AbstractThe Monte Carlo method is a common and accurate way to model neutron transport with minimal ...
The calculation of macroscopic neutron cross-sections is a fundamental part of the continuous-energy...
Monte Carlo (MC) neutron transport simulations are widely used in the nuclear community to perform r...
Monte Carlo (MC) neutron transport simulations are widely used in the nuclear community to perform r...
Monte Carlo (MC) neutron transport simulations are widely used in the nuclear community to perform r...
Monte Carlo (MC) neutron transport simulations are widely used in the nuclear community to perform r...
Monte Carlo (MC) neutron transport simulations are widely used in the nuclear community to perform r...
Monte Carlo (MC) neutron transport simulations are widely used in the nuclear community to perform r...
Monte Carlo (MC) neutron transport simulations are widely used in the nuclear community to perform r...
Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...
We describe and test a technique for carrying out energy grid searches in continuous-energy Monte Ca...
A considerable speed-up in continuous-energy Monte Carlo neutron transport calculation can be achiev...
A considerable speed-up in continuous-energy Monte Carlo neutron transport calculation can be achiev...
This research presents new code for Monte Carlo N-Particle (MCNP) to achieve an improved time during...
Monte Carlo neutron transport codes are a growing subject of research in nuclear reactor analysis. F...
AbstractThe Monte Carlo method is a common and accurate way to model neutron transport with minimal ...
The calculation of macroscopic neutron cross-sections is a fundamental part of the continuous-energy...
Monte Carlo (MC) neutron transport simulations are widely used in the nuclear community to perform r...
Monte Carlo (MC) neutron transport simulations are widely used in the nuclear community to perform r...
Monte Carlo (MC) neutron transport simulations are widely used in the nuclear community to perform r...
Monte Carlo (MC) neutron transport simulations are widely used in the nuclear community to perform r...
Monte Carlo (MC) neutron transport simulations are widely used in the nuclear community to perform r...
Monte Carlo (MC) neutron transport simulations are widely used in the nuclear community to perform r...
Monte Carlo (MC) neutron transport simulations are widely used in the nuclear community to perform r...
Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...
We describe and test a technique for carrying out energy grid searches in continuous-energy Monte Ca...
A considerable speed-up in continuous-energy Monte Carlo neutron transport calculation can be achiev...
A considerable speed-up in continuous-energy Monte Carlo neutron transport calculation can be achiev...
This research presents new code for Monte Carlo N-Particle (MCNP) to achieve an improved time during...
Monte Carlo neutron transport codes are a growing subject of research in nuclear reactor analysis. F...
AbstractThe Monte Carlo method is a common and accurate way to model neutron transport with minimal ...