4 papers
Improvement of Geant4 Neutron-HP package: Unresolved Resonance Region description with Probability Tables
M. Zmeškal, L. Thulliez, P. Tamagno +1
Whether for shielding applications or for criticality safety studies, solving the neutron transport equation with good accuracy requires to take into account the resonant structure…
The methodology for validation of cross sections in quasi monoenergetic neutron field
Zdeněk Matěj, Michal Košťál, Mitja Majerle +15
Dosimetry cross sections are fundamental quantities essential in determination of neutron fluences in points of interest in technologies under heavy radiation load. The most common…
Measurement of Dosimetrical Cross Sections with 14.05 MeV Neutrons From Compact Neutron Generator
Michal Kostal, Tomáš Czakoj, Jan Simon +11
Dosimetry cross sections are fundamental quantities necessary for neutron dosimetry using the neutron activation method. It is worth noting that the uncertainty in cross sections i…
Improvement of Geant4 Neutron-HP package: Doppler broadening of the neutron elastic scattering kernel and cross sections
M. Zmeškal, L. Thulliez, E. Dumonteil
Whether it is for shielding applications or for safety criticality studies, numerically solving the neutron transport equation with a good accuracy requires to precisely estimate t…