A Monte Carlo code for the BM 704 computer was written to study the transport of neutrons in a uniform heterogeneous lattice of cylindrical fuel assemblies. Models of the geometric and physical processes are used to obtain the neutron age and migration area; the flux as a function of position, energy, and direction; and absorption data from which thermal utilization and the multiplication constant k may be calculated. (auth
International audienceSafety analysis of innovative reactor designs requires three dimensional model...
International audienceSafety analysis of innovative reactor designs requires three dimensional model...
The Monte Carlo Model System (MCMS) for the Washington State University (WSU) Radiation Center provi...
This paper presents a new assembly-level Monte Carlo neutron transport code, specifically intended f...
This paper presents a new assembly-level Monte Carlo neutron transport code, specifically intended f...
In neutron dosimetry, calculations enable one to predict the response of a proposed dosimeter before...
Monte Carlo neutron transport codes are widely used in various reactor physics applications, traditi...
Monte Carlo neutron transport codes are widely used in various reactor physics applications, traditi...
The TUT-T5 code for the IBM-704 estimates neutron capture probabilities in a one-energy, two-dimensi...
The accurate modeling of nuclear reactors is essential to the safe and economic operation of current...
The accurate modeling of nuclear reactors is essential to the safe and economic operation of current...
"Physics and Mathematics (TID-4500, 15th Ed.).""Printed for the United States Atomic Energy Commissi...
The author of this paper recently proposed a Monte Carlo calculation algorithm to solve a complex tr...
"Bettis Atomic Power Laboratory, Pittsburgh, Pennsylvania, operated for the U.S. Atomic Energy Commi...
Safety analysis of innovative reactor designs requires three dimensional modeling to ensure a suffic...
International audienceSafety analysis of innovative reactor designs requires three dimensional model...
International audienceSafety analysis of innovative reactor designs requires three dimensional model...
The Monte Carlo Model System (MCMS) for the Washington State University (WSU) Radiation Center provi...
This paper presents a new assembly-level Monte Carlo neutron transport code, specifically intended f...
This paper presents a new assembly-level Monte Carlo neutron transport code, specifically intended f...
In neutron dosimetry, calculations enable one to predict the response of a proposed dosimeter before...
Monte Carlo neutron transport codes are widely used in various reactor physics applications, traditi...
Monte Carlo neutron transport codes are widely used in various reactor physics applications, traditi...
The TUT-T5 code for the IBM-704 estimates neutron capture probabilities in a one-energy, two-dimensi...
The accurate modeling of nuclear reactors is essential to the safe and economic operation of current...
The accurate modeling of nuclear reactors is essential to the safe and economic operation of current...
"Physics and Mathematics (TID-4500, 15th Ed.).""Printed for the United States Atomic Energy Commissi...
The author of this paper recently proposed a Monte Carlo calculation algorithm to solve a complex tr...
"Bettis Atomic Power Laboratory, Pittsburgh, Pennsylvania, operated for the U.S. Atomic Energy Commi...
Safety analysis of innovative reactor designs requires three dimensional modeling to ensure a suffic...
International audienceSafety analysis of innovative reactor designs requires three dimensional model...
International audienceSafety analysis of innovative reactor designs requires three dimensional model...
The Monte Carlo Model System (MCMS) for the Washington State University (WSU) Radiation Center provi...