201 citations · 216 across the 12 of their papers we have counts for
12 papers
ENDF/B-VIII.1: Updated Nuclear Reaction Data Library for Science and Applications
G. P. A. Nobre, R. Capote, M. T. Pigni +106
The ENDF/B-VIII.1 library is the newest recommended evaluated nuclear data file by the Cross Section Evaluation Working Group (CSEWG) for use in nuclear science and technology appl…
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,…
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…
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…
IRDFF-II: A New Neutron Metrology Library
A. Trkov, P. J. Griffin, S. P. Simakov +21
High quality nuclear data is the most fundamental underpinning for all neutron metrology applications. This paper describes the release of version II of the International Reactor D…