1 citations · 1 across the 5 of their papers we have counts for
5 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…
Validation of IRDFF-II library in VR-1 reactor field using thin targets
Michal Kostal, Evzen Losa1, Martin Schulc +9
Cross section data are fundamental quantities which affect the accuracy of all calculations in nuclear applications. A new dosimetry library IRDFF-II that contains cross section ev…
The effect of heavy reflector on neutronic parameters of core
Michal Košťál, Evžen Losa, Tomáš Czakoj +7
The reactor baffle is an important component of a nuclear reactor that fixes the location of the fuel assembly in the reactor core. The main types of baffles are called light or he…
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…