201 citations · 246 across the 8 of their papers we have counts for
8 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,…
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…
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…
Newly Evaluated Neutron Reaction Data on Chromium Isotopes
G. P. A. Nobre, M. T. Pigni, D. A. Brown +10
Neutron reaction data for the set of major chromium isotopes were reevaluated from the thermal energy range up to 20 MeV. In the low energy region, updates to the thermal values to…