3 papers
physics.comp-ph2024
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…
physics.ins-det2023
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…
nucl-ex2023
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…