Zobrazeno 1 - 10
of 529
pro vyhledávání: '"Šimon, Ján"'
Autor:
Košťál, Michal, Losa, Evžen, Simakov, Stanislav, Czakoj, Tomáš, Schulc, Martin, Šimon, Jan, Rypar, Vojtěch, Mareček, Martin, Uhlíř, Jan, Krechlerová, Alena, Peltan, Tomáš, Pošvař, Radek, Matěj, Zdeněk, Bernard, David, Trkov, Andrej, Capote, Roberto
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,p)14C, have added value for special applications, as these reactions m
Externí odkaz:
http://arxiv.org/abs/2407.07897
Autor:
Peltan, Tomáš, Vilímová, Eva, Czakoj, Tomáš, Matěj, Zdeněk, Mravec, Filip, Cvachovec, František, Šimon, Jan, Juříček, Vlastimil, Košťál, Michal, Schulc, Martin
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 to which attention is focused due to the very high-temperature reacto
Externí odkaz:
http://arxiv.org/abs/2308.16300
Autor:
Kostal, Michal, Matěj, Zdeněk, Schulc, Martin, Losa, Evžen, Šimon, Jan, Novák, Evžen, Cvachovec, František, Přenosil, Vaclav, Mravec, Filip, Czakoj, Tomáš, Rypar, Vojtěch, Trkov, Andrej, Capote, Roberto
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 cross section data, since geometric uncertainties play a much smaller role
Externí odkaz:
http://arxiv.org/abs/2307.15094
Autor:
Matěj, Zdeněk, Košťál, Michal, Majerle, Mitja, Ansorge, Martin, Losa, Evžen, Zmeškal, Marek, Schulc, Martin, Šimon, Jan, Štefánik, Milan, Novák, Jan, Koliadko, Daniil, Cvachovec, František, Mravec, Filip, Přenosil, Václav, Zach, Václav, Czakoj, Tomáš, Rypar, Vojtěch, Capote, Roberto
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 is their application to Reactor Pressure Vessel aging management, rel
Externí odkaz:
http://arxiv.org/abs/2306.09353
Autor:
Košťál, Michal, Losa, Evžen, Czakoj, Tomáš, Schulc, Martin, Šimon, Jan, Juříček, Vlastimil, Rypar, Vojtěch, Ulmanová, Jana, Trkov, Andrej, Capote, Roberto
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 heavy. The light baffle has mostly the form of steel plates with outer s
Externí odkaz:
http://arxiv.org/abs/2306.09352
Autor:
Kostal, Michal, Losa1, Evzen, Schulc, Martin, Simon, Jan, Bily, Tomas, Rypar, Vojtech, Mareček, Martin, Uhlíř, Jan, Czakoj, Tomáš, Capote, Roberto, Trkov, Andrej, Simakov, Stanislav
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 evaluations with full uncertainty quantification was developed by the In
Externí odkaz:
http://arxiv.org/abs/2306.09921
Autor:
Kostal, Michal, Losa, Evzen, Simakov, Stanislav, Schulc, Martin, Simon, Jan, Rypar, Vojtech, Mareček, Martin, Uhlíř, Jan, Czakoj, Tomáš, Trkov, Andrej, Capote, Roberto
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 experiments focused on the determination of Spectrum Averaged Cross Sections (
Externí odkaz:
http://arxiv.org/abs/2306.02835
Autor:
Kostal, Michal, Czakoj, Tomáš, Simon, Jan, Zmeskal, Marek, Schulc, Martin, Krechlerova, Alena, Peltan, Tomáš, Mravec, Filip, Cvachovec, Frantisek, Rypar, Vojtěch, Uhlar, Radim, Alexa, Petr, Harkut, Ondrej, Matej, Zdenek
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 is the major source of uncertainty in calculational predictions using n
Externí odkaz:
http://arxiv.org/abs/2306.02801
Autor:
Schulc, Martin, Kostal, Michal, Czakoj, Tomas, Novak, Evzen, Simon, Jan, Hynkova, Nella, Capote, Roberto
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 cross sections. The presented work uses only neutron standard, i.e., 25
Externí odkaz:
http://arxiv.org/abs/2306.02669
Autor:
Czakoj, Tomáš, Košťál, Michal, Novák, Evžen, Šimon, Jan, Schulc, Martin, Matěj, Zdeněk, Mravec, Filip, Cvachovec, František, Urban, Tomáš, Losa, Evžen
Publikováno v:
In Annals of Nuclear Energy February 2025 211
