The theory used in FASTER-III, a Monte Carlo computer program for the transport of neutrons and gamma rays in complex geometries, is outlined. The program includes the treatment of geometric regions bounded by quadratic and quadric surfaces with multiple radiation sources which have specified space, angle, and energy dependence. The program calculates, using importance sampling, the resulting number and energy fluxes at specified point, surface, and volume detectors. It can also calculate minimum weight shield configuration meeting a specified dose rate constraint. Results are presented for sample problems involving primary neutron, and primary and secondary photon, transport in a spherical reactor shield configuration
FASTER code for significantly reducing ducted reactor shield computation time for neutron number spe...
The work performed in the following areas is summarized: (1) Analysis of Realistic nuclear-propelled...
Appropriate importance function and sampling scheme facilitates the application of the Monte Carlo m...
Monte Carlo calculations of neutron and gamma ray transport and minimum shield weight for mobile nuc...
Neutron flux and gamma ray source edit computer program for design and analysis of radiation shields...
A study program of radiation shielding against the deleterious effects of nuclear radiation on man a...
Fortran analytic solution of transport equations by random sampling in radiation shielding design an...
TIC-TOC-TOE computer program for radiation shielding design and analysis in nuclear rocket system
The theoretical treatment of the transport of particles and radiation gives rise to problems of grea...
Eight computer programs make up a nine volume synthesis containing two design methods for nuclear ro...
The theoretical treatment of the transport of particles and radiationgives rise to problems of great...
A radiation shield internal to the NERVA nuclear rocket reactor required to limit the neutron and ph...
The nuclear reactor emits various kinds of nuclear radiations during operation. However, the main co...
A neutron transport algorithm including both elastic and nonelastic particle interaction processes f...
The research of the neutron induced Single Event Effect (SEE) at aircraft altitudes or at ground lev...
FASTER code for significantly reducing ducted reactor shield computation time for neutron number spe...
The work performed in the following areas is summarized: (1) Analysis of Realistic nuclear-propelled...
Appropriate importance function and sampling scheme facilitates the application of the Monte Carlo m...
Monte Carlo calculations of neutron and gamma ray transport and minimum shield weight for mobile nuc...
Neutron flux and gamma ray source edit computer program for design and analysis of radiation shields...
A study program of radiation shielding against the deleterious effects of nuclear radiation on man a...
Fortran analytic solution of transport equations by random sampling in radiation shielding design an...
TIC-TOC-TOE computer program for radiation shielding design and analysis in nuclear rocket system
The theoretical treatment of the transport of particles and radiation gives rise to problems of grea...
Eight computer programs make up a nine volume synthesis containing two design methods for nuclear ro...
The theoretical treatment of the transport of particles and radiationgives rise to problems of great...
A radiation shield internal to the NERVA nuclear rocket reactor required to limit the neutron and ph...
The nuclear reactor emits various kinds of nuclear radiations during operation. However, the main co...
A neutron transport algorithm including both elastic and nonelastic particle interaction processes f...
The research of the neutron induced Single Event Effect (SEE) at aircraft altitudes or at ground lev...
FASTER code for significantly reducing ducted reactor shield computation time for neutron number spe...
The work performed in the following areas is summarized: (1) Analysis of Realistic nuclear-propelled...
Appropriate importance function and sampling scheme facilitates the application of the Monte Carlo m...