240 citations · 1.7k across the 23 of their papers we have counts for
23 papers
FENDL: A library for fusion research and applications
G. Schnabel, D. L. Aldama, T. Bohm +28
The Fusion Evaluated Nuclear Data Library (FENDL) is a comprehensive and validated collection of nuclear cross section data coordinated by the International Atomic Energy Agency (I…
Characterisation of neutron field in large graphite insertion in special core of the LR-0 Reactor
Tomáš Peltan, Eva Vilímová, Tomáš Czakoj +7
Graphite is important reactor material used as a neutron moderator in various reactor designs. It is not only structural material used in previous reactors design but even material…
Benchmarking of stainless steel cube neutron leakage in Research Center Rez
Michal Kostal, Zdeněk Matěj, Martin Schulc +10
The integral experiments covering the neutron leakage from geometrically simple assemblies with a 252Cf source inside are very valuable tools usable in validation of transport cros…
Impact of Reactor Neutron Spectrum on Measured Spectrum Averaged Cross Sections
Michal Kostal, Evzen Losa, Stanislav Simakov +8
The cross section averaged over 235U thermal-neutron induced fission spectrum is a fundamental quantity that can be used in evaluation and validation of nuclear data. Many experime…
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…
Spectrum averaged cross section measurements of lutetium using standard 252Cf neutron source
Martin Schulc, Michal Kostal, Tomas Czakoj +4
The spectrum averaged cross section (SACS) in standard neutron field is a preferable tool for cross section validation. There are very few measurements involving lutetium neutron c…