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  1. Article ; Online: The spectrum-averaged cross section investigation of

    Krechlerová, Alena / Košťál, Michal / Losa, Evžen / Schulc, Martin / Czakoj, Tomáš / Tisseur, David / Novák, Evžen / Šimon, Jan / Thiollay, Nicolas

    Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine

    2024  Volume 209, Page(s) 111306

    Abstract: The spectrum averaged cross sections (SACS) in standard neutron field, e.g. ...

    Abstract The spectrum averaged cross sections (SACS) in standard neutron field, e.g.
    Language English
    Publishing date 2024-03-30
    Publishing country England
    Document type Journal Article
    ZDB-ID 1142596-9
    ISSN 1872-9800 ; 0883-2889 ; 0969-8043
    ISSN (online) 1872-9800
    ISSN 0883-2889 ; 0969-8043
    DOI 10.1016/j.apradiso.2024.111306
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  2. Article ; Online: MEASUREMENT OF PROMPT GAMMAS OF INELASTIC SCATTERING IN D2O SPHERE USING AMBE SOURCE.

    Czakoj, Tomáš / Košťál, Michal / Novák, Evžen / Losa, Evžen / Šimon, Jan / Schulc, Martin / Matěj, Zdeněk

    Radiation protection dosimetry

    2022  Volume 198, Issue 9-11, Page(s) 698–703

    Abstract: The inelastic neutron scattering is often followed by the emission of gamma photon. As the prompt gammas have a discrete level character they can be used for the identification of nuclides. Because of this fact, a good knowledge of photon production from ...

    Abstract The inelastic neutron scattering is often followed by the emission of gamma photon. As the prompt gammas have a discrete level character they can be used for the identification of nuclides. Because of this fact, a good knowledge of photon production from inelastic scattering is important. Described research deals with the measurement of gamma originated from inelastic scattering of neutrons on 16O. The 241Am-Be was used as a neutron source because of its high average neutron energy. The oxygen in form of heavy water was used for maximization of neutron flux on oxygen and minimization of background gammas' production, namely 2223 keV gammas accompanying capture on hydrogen 1H. The gamma spectrum was measured by HPGe and the stilbene detector. The HPGe measured quantities are comparted with calculation and discrepancies between measured and calculated gamma fluxes are reported. Stilbene measurement shows indistinguishability of gamma peaks above 6 MeV.
    Language English
    Publishing date 2022-08-22
    Publishing country England
    Document type Journal Article
    ZDB-ID 225912-6
    ISSN 1742-3406 ; 0144-8420
    ISSN (online) 1742-3406
    ISSN 0144-8420
    DOI 10.1093/rpd/ncac122
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  3. Article ; Online: Spectrum averaged cross section measurements of lutetium using standard

    Schulc, Martin / Košťál, Michal / Czakoj, Tomáš / Novák, Evžen / Šimon, Jan / Hynková, Nella / Capote, Roberto

    Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine

    2022  Volume 188, Page(s) 110378

    Abstract: The spectrum averaged cross section (SACS) in a standard neutron field is a preferable tool for cross section validation. The presented work uses only neutron standard, i.e., ...

    Abstract The spectrum averaged cross section (SACS) in a standard neutron field is a preferable tool for cross section validation. The presented work uses only neutron standard, i.e.,
    MeSH term(s) Lutetium/chemistry ; Models, Theoretical ; Neutrons ; Radioisotopes/chemistry
    Chemical Substances Radioisotopes ; Lutetium (5H0DOZ21UJ)
    Language English
    Publishing date 2022-07-12
    Publishing country England
    Document type Journal Article
    ZDB-ID 1142596-9
    ISSN 1872-9800 ; 0883-2889 ; 0969-8043
    ISSN (online) 1872-9800
    ISSN 0883-2889 ; 0969-8043
    DOI 10.1016/j.apradiso.2022.110378
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  4. Article ; Online: Characterization of the secondary neutron field inside a cyclotron for production of radiopharmaceuticals.

    Zmeškal, Marek / Košťál, Michal / Czakoj, Tomáš / Šimon, Jan / Majerle, Mitja / Zach, Václav / Lebeda, Ondřej / Vadják, Šimon / Antoš, Michal / Matěj, Zdeněk

    Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine

    2023  Volume 199, Page(s) 110865

    Abstract: During production of radiopharmaceuticals, the radiation situation in cyclotron pit is an important parameter, which is being monitored to ensure fulfilment of the limits and conditions of safe operation. The neutron flux in the structural components of ... ...

    Abstract During production of radiopharmaceuticals, the radiation situation in cyclotron pit is an important parameter, which is being monitored to ensure fulfilment of the limits and conditions of safe operation. The neutron flux in the structural components of the accelerator is also an important parameter, because the secondary neutrons are responsible for activation of cyclotron structural components and may even affect structural changes in it. This paper aims to characterize the neutron field in inner positions of medical accelerator IBA 18/9 by activation detectors and by means of scintillation spectrometry. The backward angle measurement was realized also in special liquid water target (H
    Language English
    Publishing date 2023-05-23
    Publishing country England
    Document type Journal Article
    ZDB-ID 1142596-9
    ISSN 1872-9800 ; 0883-2889 ; 0969-8043
    ISSN (online) 1872-9800
    ISSN 0883-2889 ; 0969-8043
    DOI 10.1016/j.apradiso.2023.110865
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  5. Article ; Online: Validation of nickel isotopes neutron cross sections using nickel spherical benchmark.

    Schulc, Martin / Košťál, Michal / Novák, Evžen / Czakoj, Tomáš

    Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine

    2018  Volume 140, Page(s) 247–251

    Abstract: The fast leakage neutron spectra have been measured on spherical nickel benchmark assembly of diameter 50 cm. ... ...

    Abstract The fast leakage neutron spectra have been measured on spherical nickel benchmark assembly of diameter 50 cm. The
    Language English
    Publishing date 2018-07-24
    Publishing country England
    Document type Journal Article
    ZDB-ID 1142596-9
    ISSN 1872-9800 ; 0883-2889 ; 0969-8043
    ISSN (online) 1872-9800
    ISSN 0883-2889 ; 0969-8043
    DOI 10.1016/j.apradiso.2018.07.030
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  6. Book ; Online: Characterisation of neutron field in large graphite insertion in special core of the LR-0 Reactor

    Peltan, Tomáš / Vilímová, Eva / Czakoj, Tomáš / Matěj, Zdeněk / Mravec, Filip / Cvachovec, František / Šimon, Jan / Juříček, Vlastimil / Košťál, Michal / Schulc, Martin

    2023  

    Abstract: 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 reactor ... ...

    Abstract 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 reactor design, which uses graphite as moderator and reflector. Due to the well-characterised cross-section of graphite, it is also a good candidate for neutron shaping experiments. In this kind of experiment, the neutron spectra are modified to the unconventional shape of neutron spectra which can be used to validate cross-section. This paper deals with validation of neutron field in graphite block surrounded by driver core arranged in large special core in LR-0 reactor. The experimentally determined shape of neutron spectra and spatial distribution of neutron flux is compared with the calculation. It is worth noting that the agreement for flux distribution is satisfactory in regions below the moderator level.
    Keywords Physics - Instrumentation and Detectors
    Subject code 660
    Publishing date 2023-07-31
    Publishing country us
    Document type Book ; Online
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  7. Book ; Online: The effect of heavy reflector on neutronic parameters of core

    Košťál, Michal / Losa, Evžen / Czakoj, Tomáš / Schulc, Martin / Šimon, Jan / Juříček, Vlastimil / Rypar, Vojtěch / Ulmanová, Jana / Trkov, Andrej / Capote, Roberto

    2023  

    Abstract: 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 space ...

    Abstract 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 space filled by water, and the heavy baffle is mostly a forged steel element. Both concepts have advantages as well as disadvantages. In the case of the light baffle, one does not need to solve the issue of void swelling, but the neutron economy is not ideal, while the heavy baffle has a good neutron economy, but void swelling is an issue. This paper deals with the effect of the heavy VVER-1000 baffle on criticality. Criticality was measured using a well-defined core composed of 6 fuel assemblies moved to a simulator of the VVER-1000 internals, which is located at the LR-0 reactor. The experiments confirm the fact that the water filling the cooling channels in the baffle has a strong neutron absorbing effect. The keff calculated using the ENDF/B-VIII.0 library significantly underpredicts the experiment, whereas calculations using a new evaluation of 56Fe by the IAEA (INDEN collaboration) give a better agreement. Generally, the presented results are suitable for validation of iron cross sections.
    Keywords Physics - Instrumentation and Detectors
    Subject code 660
    Publishing date 2023-06-05
    Publishing country us
    Document type Book ; Online
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  8. Article ; Online: Constraining high energy tail of

    Schulc, Martin / Košťál, Michal / Šimon, Jan / Brijar, Filip / Czakoj, Tomáš / Malý, Jiří Pipster

    Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine

    2020  Volume 166, Page(s) 109313

    Abstract: There is a lack of reliable experiments aiming at the prompt fission neutron spectrum ... ...

    Abstract There is a lack of reliable experiments aiming at the prompt fission neutron spectrum of
    Language English
    Publishing date 2020-07-26
    Publishing country England
    Document type Journal Article
    ZDB-ID 1142596-9
    ISSN 1872-9800 ; 0883-2889 ; 0969-8043
    ISSN (online) 1872-9800
    ISSN 0883-2889 ; 0969-8043
    DOI 10.1016/j.apradiso.2020.109313
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  9. Book ; Online: Impact of Reactor Neutron Spectrum on Measured Spectrum Averaged Cross Sections

    Kostal, Michal / Losa, Evzen / Simakov, Stanislav / Schulc, Martin / Simon, Jan / Rypar, Vojtech / Mareček, Martin / Uhlíř, Jan / Czakoj, Tomáš / Trkov, Andrej / Capote, Roberto

    2023  

    Abstract: 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 (SACS) ...

    Abstract 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 (SACS) in 235U(nth,f). Prompt Fission Neutron Spectrum (PFNS) in light water reactors using enriched uranium fuel. In these reactors, there is already some amount of water moderator between the uranium fuel and the irradiated sample. Due to the decrease of hydrogen cross-section with neutron energy, the high energy tail of the reactor spectrum in cores with water moderator may be harder than the pure PFNS. This paper aims to compare the shape of the actual reactor spectrum in various core positions of a research light-water reactor differing each from other by the effective water thickness. The spectrum shape is determined both by calculations and experimentally using various high energy threshold reactions. The impact of the photo-nuclear reactions ({\gamma},n) competing with (n,2n) in production of the same residual nucleus was shown to be less than a percent for most of studied dosimeters. An important exception was found for 197Au(n,2n) 196Au dosimeter irradiated in the outcore channel where a notable photo-neutron contribution to the production of 196Au is caused by the neutron production from the high energy {\gamma}-rays from thermal-neutron capture in 54Fe. The corresponding ENDF/B-VIII.0 data turned out to underestimate such {\gamma}-yield by 40% in comparison with ENDF/B-VI.8. This has improved but however not resolved the disagreement between our measurement and calculations. The remaining deficiency was attributed to the underestimation of the evaluated cross section IAEA/PD-2019 for the 197Au({\gamma},n) cross section near the reaction threshold. The later was confirmed by comparison with existing measured data.
    Keywords Nuclear Experiment
    Subject code 660
    Publishing date 2023-06-05
    Publishing country us
    Document type Book ; Online
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  10. Article ; Online: Testing of various neutron filters in reference neutron field in LR-0 reactor for nuclear data validation and verification.

    Košťál, Michal / Losa, Evžen / Schulc, Martin / Czakoj, Tomáš / Peltan, Tomáš / Šimon, Jan / Juříček, Vlastimil / Rypar, Vojtěch / Thiollay, Nicolas / Destouches, Christophe / Radulović, Vladimir / Trkov, Andrej / Capote, Roberto

    Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine

    2020  Volume 169, Page(s) 109566

    Abstract: Neutron activation analysis is the reference method used for offline determination of the neutron flux density in defined positions. It can be used in the nuclear energy industry-as well as in medical- or space applications. For accurate neutron flux ... ...

    Abstract Neutron activation analysis is the reference method used for offline determination of the neutron flux density in defined positions. It can be used in the nuclear energy industry-as well as in medical- or space applications. For accurate neutron flux evaluation, well-known and reliable cross sections are needed. In the thermal and fast energy region, many reliable monitoring reactions exists, however, in case of the epithermal and intermediate energy region, there are practically no dosimetry nuclear reactions sensitive specifically in this energy range. Due to this fact, both new data are being measured and methodologies are under development to describe and test this energy region. It was found that various neutron filters can be used to cut parts of neutron spectra and thus methodology based on spectrum filtering could potentially be employed to survey cross sections of interest. It this paper, the use of 3 different filters - B
    Language English
    Publishing date 2020-12-24
    Publishing country England
    Document type Journal Article
    ZDB-ID 1142596-9
    ISSN 1872-9800 ; 0883-2889 ; 0969-8043
    ISSN (online) 1872-9800
    ISSN 0883-2889 ; 0969-8043
    DOI 10.1016/j.apradiso.2020.109566
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