The code NEDIS allows the calculation of neutron production rate and continuous energy spectra due to (α,n) reaction on Li, Be, B, C, O, F, Ne, Na Mg, Al, Si, P, S, Cl, Ar, K, and Ca. It accounts for anisotropic angular distribution of neutrons of (α,n) reaction in centre-of- mass system and dimensions of alpha emitting source material particles. Spontaneous fission spectra are calculated with evaluated half-life, spontaneous fission branching, ν- averaged per fission, and Watt spectrum parameters. The results of calculations by NEDIS can be used as input for Monte Carlo simulation for materials that will be used in radiation shielding and for underground neutron experiment
The prompt fission neutron multiplicity and spectra of actinides are nuclear data of crucial importa...
The creation of a grouping constant system for the calculation of heat release from the interaction ...
New, self-consistent, neutron-induced reaction cross-section calculations for 235,238U, 237Np, and 2...
SOURCES 4A is a computer code that determines neutron production rates and spectra from ({alpha},n) ...
The 13C (α,n)16O reaction cross-section is important data for nuclear physics, astrophysical, and ne...
International audienceMany years have been devoted to study the behaviour of solids submitted to imp...
In many systems, it is imperative to have accurate knowledge of all significant sources of neutrons ...
Neutron production yields and energy distributions from (α,n) reactions in light elements were calcu...
Various parameters which are relevant to an understanding of radiation effects in metals have been e...
In the experimental section of this project, the energy spectrum of fast neutrons is measured, after...
A global potential-driving model with well-determined parameters is proposed by uniting the empirica...
The prompt fission neutron multiplicity and spectra of actinides are nuclear data of crucial importa...
In the present work the neutron emission spectra from a graphite cube, and from natural uranium, lit...
ABSTRACT During the next decade experiments will be performed at a number of neutron sources in an e...
13th International Conference on Emerging Nuclear Energy Systems 2007, ICENES 2007 -- 3 June 2007 th...
The prompt fission neutron multiplicity and spectra of actinides are nuclear data of crucial importa...
The creation of a grouping constant system for the calculation of heat release from the interaction ...
New, self-consistent, neutron-induced reaction cross-section calculations for 235,238U, 237Np, and 2...
SOURCES 4A is a computer code that determines neutron production rates and spectra from ({alpha},n) ...
The 13C (α,n)16O reaction cross-section is important data for nuclear physics, astrophysical, and ne...
International audienceMany years have been devoted to study the behaviour of solids submitted to imp...
In many systems, it is imperative to have accurate knowledge of all significant sources of neutrons ...
Neutron production yields and energy distributions from (α,n) reactions in light elements were calcu...
Various parameters which are relevant to an understanding of radiation effects in metals have been e...
In the experimental section of this project, the energy spectrum of fast neutrons is measured, after...
A global potential-driving model with well-determined parameters is proposed by uniting the empirica...
The prompt fission neutron multiplicity and spectra of actinides are nuclear data of crucial importa...
In the present work the neutron emission spectra from a graphite cube, and from natural uranium, lit...
ABSTRACT During the next decade experiments will be performed at a number of neutron sources in an e...
13th International Conference on Emerging Nuclear Energy Systems 2007, ICENES 2007 -- 3 June 2007 th...
The prompt fission neutron multiplicity and spectra of actinides are nuclear data of crucial importa...
The creation of a grouping constant system for the calculation of heat release from the interaction ...
New, self-consistent, neutron-induced reaction cross-section calculations for 235,238U, 237Np, and 2...