Zobrazeno 1 - 10
of 207
pro vyhledávání: '"Trkov Andrej"'
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:
Kostal Michal, Czakoj Tomas, Losa Evzen, Schulc Martin, Juříček Vlastimil, Šimon Jan, Rypar Vojtěch, Mareček Martin, Capote Roberto, Trkov Andrej
Publikováno v:
EPJ Web of Conferences, Vol 247, p 09018 (2021)
The cross section is a fundamental quantity which affects the accuracy of Monte Carlo simulations widely used in nuclear applications. A new dosimetry library IRDFF-II that contains cross section evaluations that include full uncertainty quantificati
Externí odkaz:
https://doaj.org/article/34c17d40715443ee985fa9fca460c291
Autor:
Fausser Clément, Thiollay Nicolas, Destouches Christophe, Barbot Loïc, Fourmentel Damien, Geslot Benoît, De Izarra Grégoire, Gruel Adrien, Grégoire Gilles, Domergue Christophe, Radulović Vladimir, Goričanec Tanja, Ambrožič Klemen, Žerovnik Gasper, Lengar Igor, Trkov Andrej, Štancar Žiga, Pungerčič Anže, Snoj Luka
Publikováno v:
EPJ Web of Conferences, Vol 253, p 04018 (2021)
Constant improvements of the computational power and methods as well as demands of accurate and reliable measurements for reactor operation and safety require a continuous upgrade of the instrumentation. In particular, nuclear sensors used in nuclear
Externí odkaz:
https://doaj.org/article/04fc93ad7376422590abcacd8e357f51
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:
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:
Capote Roberto, Trkov Andrej
Publikováno v:
EPJ Nuclear Sciences & Technologies, Vol 4, p 27 (2018)
Key reactions have been selected to compare JEFF-3.3 (CIELO 2) and IAEA CIELO (CIELO 1) evaluated nuclear data files for neutron induced reactions on 235U and 238U targets. IAEA CIELO evaluation uses reaction models to construct the evaluation prior,
Externí odkaz:
https://doaj.org/article/e6de22e78c134c1a8bf9bec2d8c4e1c9
Publikováno v:
EPJ Web of Conferences, Vol 146, p 02011 (2017)
In August 2016, following the recent effort within the Collaborative International Evaluated Library Organization (CIELO) pilot project to improve the neutron cross sections of 235U, Oak Ridge National Laboratory (ORNL) collaborated with the Internat
Externí odkaz:
https://doaj.org/article/b5d872b15248426885cf18116a6d67b1
Autor:
Fischer Ulrich, Avrigeanu Marilena, Avrigeanu Vlad, Cabellos Oscar, Dzysiuk Natalia, Koning Arjan, Klix Axel, Konobeev Alexander, Kodeli Ivo, Leeb Helmut, Leichtle Dieter, Nunnenmann Elena, Packer Lee, Rochman Dimitri, Pereslavtsev Pavel, Sauvan Patrick, Trkov Andrej
Publikováno v:
EPJ Web of Conferences, Vol 146, p 09003 (2017)
The European approach for the development of nuclear data for fusion technology applications is presented. Related R&D activities are conducted by the Consortium on Nuclear Data Development and Analysis for Fusion to satisfy the nuclear data needs of
Externí odkaz:
https://doaj.org/article/2d3a0aabd76e4795aff72185c945cc9e