1 citations · 1 across the 10 of their papers we have counts for
10 papers
Aluminium fast neutron leakage spectrum validation
Martin Schulc, Tomáš Czakoj, Evžen Novák +7
Aluminum is a crucial material in the nuclear industry, valued for its ability to perform reliably over time. The manuscript focuses on validating aluminum neutron transport librar…
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…
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 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…
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…
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…