The MCNP distributions include sets of pre-calculated thermal scattering libraries but these libraries are available for several temperature steps only. In order to achieve reliable results it is suitable to process the cross section libraries for the desired temperature. In general, there are three methods to process these thermal scattering libraries for the desired temperatures. This paper deals with the comparison of these three methods on the basis of several benchmarks and on the basis of a thermal transient experiment of a WWER-440 reactor. The choice is up to the MCNP user but unfortunately very few studies concerning the comparison have been published so far. Therefore conclusions and results presented in this paper may help the us...
In order to improve the design and safety of thermal nuclear reactors and for verification of critic...
To improve the evaluations in thermal scattering sub-libraries, a set of thermal neutron scattering ...
An accurate representation of the scattering of neutrons by the materials used to build cold sources...
Convenient access to accurate nuclear data, particularly data describing low-energy neutrons, is cru...
Thermal motion of nuclides has a significant effect on the reaction probabilities and scattering kin...
THERMAL is designed to calculate neutron thermal scattering that is elastic and isotropic in the cen...
International audienceImprovements in determination of the thermal scattering law of moderator mater...
Modern multi-physics codes, often employed in the simulation and development of thermal nuclear syst...
Validation of the accuracy of S(α, β) thermal scattering law (TSL) evaluations for moderator materia...
One of the longstanding obstacles to the use of the MCNP Monte Carlo code' for reactor physics calcu...
A direct comparison of transient thermal calculations was made with the heat transfer codes HEATING5...
A new method to obtain Doppler broadened cross sections has been implemented into MCNP, removing the...
GEANT4 is a Monte Carlo code originally implemented for high-energy physics applications and is well...
Thermal neutron scattering cross-section data for light water available in the major nuclear data li...
International audienceWith the advancements in technology (both experimental and computational) the ...
In order to improve the design and safety of thermal nuclear reactors and for verification of critic...
To improve the evaluations in thermal scattering sub-libraries, a set of thermal neutron scattering ...
An accurate representation of the scattering of neutrons by the materials used to build cold sources...
Convenient access to accurate nuclear data, particularly data describing low-energy neutrons, is cru...
Thermal motion of nuclides has a significant effect on the reaction probabilities and scattering kin...
THERMAL is designed to calculate neutron thermal scattering that is elastic and isotropic in the cen...
International audienceImprovements in determination of the thermal scattering law of moderator mater...
Modern multi-physics codes, often employed in the simulation and development of thermal nuclear syst...
Validation of the accuracy of S(α, β) thermal scattering law (TSL) evaluations for moderator materia...
One of the longstanding obstacles to the use of the MCNP Monte Carlo code' for reactor physics calcu...
A direct comparison of transient thermal calculations was made with the heat transfer codes HEATING5...
A new method to obtain Doppler broadened cross sections has been implemented into MCNP, removing the...
GEANT4 is a Monte Carlo code originally implemented for high-energy physics applications and is well...
Thermal neutron scattering cross-section data for light water available in the major nuclear data li...
International audienceWith the advancements in technology (both experimental and computational) the ...
In order to improve the design and safety of thermal nuclear reactors and for verification of critic...
To improve the evaluations in thermal scattering sub-libraries, a set of thermal neutron scattering ...
An accurate representation of the scattering of neutrons by the materials used to build cold sources...