4 papers
Measurement of Spectrum Averaged Cross Sections in LR-0 Benchmark Reference Neutron Field
Michal Košťál, Evžen Losa, Stanislav Simakov +13
The measured and evaluated excitation functions are fundamental quantities that affect the accuracy of all calculations in nuclear applications. Some cross sections, such as 14N(n,…
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…
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…