Research to establish a general method to assess the performance and reliability of computer codes for the numerical approximation of linear operators is reported. The neutron transport operator was chosen as model. The general approach to solving the error problem and the use of benchmarks are sketched. This report contains only a brief administrative summary; references are given to forty reports and publications that contain detailed information. (RWR
A general numerical procedure, called the discrete S/sub n/ method, for solving the neutron transpor...
Several alternative approximations of neutron transport have been proposed in years to move around t...
The spectral element method can be used to deal with the spatial operators of neutron transport prob...
The objectives of this research are to develop mathematically and computationally founded criteria f...
The objectives of the work are to develop mathematically and computationally founded for the design ...
The purpose of this talk is to introduce: • Several types of neutron transport problems in the pract...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
This paper presents a methodology developed and implemented in the neutron transport code STREAM to ...
Because of the requirement of accountability and quality control in the scientific world, a demand f...
International audience'QUADOS', a Concerted Action of the European Commission, has run an intercompa...
Consulta en la Biblioteca ETSI Industriales (9055)[EN] The rapid development of computer systems and...
The computer code block VENTURE, designed to solve multigroup neutronics problems with application o...
Thesis: Ph. D. in Computational Nuclear Science and Engineering, Massachusetts Institute of Technolo...
A Monte Carlo code for the BM 704 computer was written to study the transport of neutrons in a unifo...
Abstract: The description of methods and corresponding codes for solving the multigroup tr...
A general numerical procedure, called the discrete S/sub n/ method, for solving the neutron transpor...
Several alternative approximations of neutron transport have been proposed in years to move around t...
The spectral element method can be used to deal with the spatial operators of neutron transport prob...
The objectives of this research are to develop mathematically and computationally founded criteria f...
The objectives of the work are to develop mathematically and computationally founded for the design ...
The purpose of this talk is to introduce: • Several types of neutron transport problems in the pract...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
This paper presents a methodology developed and implemented in the neutron transport code STREAM to ...
Because of the requirement of accountability and quality control in the scientific world, a demand f...
International audience'QUADOS', a Concerted Action of the European Commission, has run an intercompa...
Consulta en la Biblioteca ETSI Industriales (9055)[EN] The rapid development of computer systems and...
The computer code block VENTURE, designed to solve multigroup neutronics problems with application o...
Thesis: Ph. D. in Computational Nuclear Science and Engineering, Massachusetts Institute of Technolo...
A Monte Carlo code for the BM 704 computer was written to study the transport of neutrons in a unifo...
Abstract: The description of methods and corresponding codes for solving the multigroup tr...
A general numerical procedure, called the discrete S/sub n/ method, for solving the neutron transpor...
Several alternative approximations of neutron transport have been proposed in years to move around t...
The spectral element method can be used to deal with the spatial operators of neutron transport prob...