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    Special Issue: Research Center Řež: Nuclear-Engineering Activities in 2020 

    Source: Journal of Nuclear Engineering and Radiation Science:;2021:;volume( 007 ):;issue: 002:;page 020301-1
    Author(s): Košťál, Michal; Schulc, Martin
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: This special issue is dedicated primarily to research performed in the Research Centre Řež Centrum Výzkumu Řež (CVŘ hereafter) during the Research for SUSEN (R4S) project (project solved in CVŘ), which is the follow-up of ...
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    Methodology of 63Cu(n,2n)62Cu Reaction Rate Measurement 

    Source: Journal of Nuclear Engineering and Radiation Science:;2020:;volume( 007 ):;issue: 002:;page 024503-1
    Author(s): Schulc, Martin; Košťál, Michal; Šimon, Jan; Novák, Evžen
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: This paper presents the measurement of the spectrum-averaged cross section (SACS) of 63Cu(n,2n)62Cu reaction in 252Cf spontaneous fission neutron spectrum. The SACS in the 252Cf spectrum was chosen as a validation tool ...
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    Investigation of 127I(n,2n)126I and 23Na(n,2n)22Na Reactions Using 252Cf Neutron Source 

    Source: Journal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 003:;page 30918
    Author(s): Schulc, Martin; Košťál, Michal; Novák, Evžen; Šimon, Jan; Burianová, Nicola
    Publisher: American Society of Mechanical Engineers (ASME)
    Abstract: This work deals with 23Na(n,2n)22Na and 127I(n,2n)126I reactions in the 252Cf spontaneous fission neutron source. 252Cf neutron source with approximate emission of 6·× 108 n/s was employed for the irradiation of sodium ...
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    Testing Oxygen Nuclear Data Libraries in Research Center Rez 

    Source: Journal of Nuclear Engineering and Radiation Science:;2020:;volume( 007 ):;issue: 002:;page 021501-1
    Author(s): Schulc, Martin; Košťál, Michal; Novák, Evžen; Šimon, Jan; Leal, Luiz
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Oxygen belongs to the group of the most important isotopes in the nuclear data field. The aim of this paper is validate various oxygen nuclear data libraries in different scenarios with high content of oxygen. For this ...
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    The Use of Polycarbonate as Dosimeter of High Doses 

    Source: Journal of Nuclear Engineering and Radiation Science:;2021:;volume( 007 ):;issue: 002:;page 022003-1
    Author(s): Zoul, David; Koplová, Markéta; Rosnecký, Vít; Košťál, Michal; Vinš, Miroslav; Šimon, Jan; Schulc, Martin; Cabalka, Martin; Kučera, Jan; Strunga, Vladimír
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Dosimetry of high doses of ionizing radiation is a method widely used not only in the field of basic and applied research but also in various industries. High-dose irradiation is used in the sterilization of foodstuffs and ...
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    Benchmarking Fast Neutrons Leakage Spectrum From Copper Block With 252Cf Source in Center 

    Source: Journal of Nuclear Engineering and Radiation Science:;2023:;volume( 009 ):;issue: 003:;page 32001-1
    Author(s): Czakoj, Tomáš; Košťál, Michal; Schulc, Martin; Rypar, Vojtěch; Novák, Evžen; Losa, Evžen
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Copper is an important material for the nuclear industry; therefore, the correct copper cross section are essential. This paper deals with benchmarking the fast neutron leakage spectrum from a copper block with an intense ...
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    The Effect of Iron Cross-Section in Thermal Region on Neutron Transport in VVER-1000 Mock-Up in LR-0 Reactor 

    Source: Journal of Nuclear Engineering and Radiation Science:;2017:;volume( 003 ):;issue: 001:;page 11019
    Author(s): Schulc, Martin; Košťál, Michal; Harutyunyan, Davit; Švadlenková, Marie; Rypar, Vojtěch; Milčák, Ján; Kolros, Antonín
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The iron cross-section in thermal regions influences the thermal neutron flux prediction in steel structural components of reactors and also in regions adjoining them. The thermal neutron flux level is proportional to pin ...
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    Measurement of Selected Differential Cross Sections in 235U Spectrum 

    Source: Journal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 003:;page 30906
    Author(s): Burianová, Nicola; Košt´ál, Michal; Schulc, Martin; Šimon, Jan; Mareček, Martin; Uhlíř, Jan
    Publisher: American Society of Mechanical Engineers (ASME)
    Abstract: This paper describes the measurement of 55Mn(n,2n) and 127I(n,2n) reaction rates in a well-defined reactor field in a special core of LR-0 reactor. The reaction rates were derived using gamma-spectrometry by measuring gamma ...
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    Testing of Scintillation Detectors in Quasi-Monoenergetic Neutron Spectra in a Silicon Filtered Neutron Beam at the LVR-15 Research Reactor 

    Source: Journal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 003:;page 30915
    Author(s): Košťál, Michal; Matěj, Zdeněk; Mravec, Filip; Cvachovec, František; Schulc, Martin; Juříček, Vlastimil; Rypar, Vojtěch; Šoltés, Jaroslav; Losa, Evžen; Viererbl, Ladislav
    Publisher: American Society of Mechanical Engineers (ASME)
    Abstract: With increasing needs of neutron detection in energy and homeland security sectors, there is an aim in the development of new suitable detection materials with possible n/g separation and also satisfactory resolution. This ...
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    The Application of Silicon-Filtered Beam in the Validation of Iron Cross Sections by Deep Penetration Experiments 

    Source: Journal of Nuclear Engineering and Radiation Science:;2021:;volume( 007 ):;issue: 002:;page 022005-1
    Author(s): Juříček, Vlastimil; Košťál, Michal; Losa, Evžen; Czakoj, Tomáš; Matěj, Zdeněk; Cvachovec, František; Schulc, Martin; Šimon, Jan; Mravec, Filip; Přenosil, Václav; Rypar, Vojtěch
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: This paper summarizes the issue of the validation of the silicon-filtered neutron beam transport in the deep neutron transport penetration experiment in iron. Iron is an essential structural material important for nuclear ...
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