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  • image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/
    Authors: Hussein Abdulkareem Saleh Abushamah; Ondřej Burian; Radek Škoda;

    Carbon-free thermally driven district cooling systems (DCS) can effectively mitigate the excessive electricity consumption and carbon emissions associated with the cooling sector. This study proposes a DCS that employs nuclear heat as the primary energy source. The system comprises three main subsystems: heat station, heat transmission, and cooling station. A heat-only small modular reactor called Teplator, gas boilers, and heat storage are considered to supply the heat required to drive absorption chillers; cold storage and compression chillers are the supplementary units. The technoeconomic aspects of the system are formulated, and an algorithm is developed to determine the optimal design and operation. The method is examined for supplying a typical cooling demand profile with a peak of 2050 MWc. The resulting optimized design includes 11 nuclear plants (150 MWt each), 20 000 MWth heat storage, and 1.9 m diameter heat supply/return pipes. Absorption chillers with a total capacity of 1424 MWc are determined, covering 92% of the total cooling demand, and 244 MWc of compression chillers and 20 000 MWch of cold storage are found to cover the peak and enhance the load following. This system saved 69% of the electricity consumption and carbon emissions and 34% of the costs compared with an electric-based scenario.

    image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/ Digital Library Univ...arrow_drop_down
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    Digital Library University of West Bohemia
    Other literature type . Article . 2023 . Peer-reviewed
    image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/
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      image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/ Digital Library Univ...arrow_drop_down
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      Digital Library University of West Bohemia
      Other literature type . Article . 2023 . Peer-reviewed
      image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/
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  • image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/
    Authors: Vilcsek, Igor; Stach, Ondřej; Kříž, Antonín;

    For nuclear energy, fusion arc welding is one of the key technologies not only for production of equipment, but also for its maintenance, assembly and repair. Due to the fact that there is a radioactive medium inside the facility, the leakage of which could have catastrophic consequences for humans and the environment. The article briefly presents the results and experiences from the application of automatic orbital welding. A valuable finding is not only the debugging of the welding process, but also the definition of boundary conditions for achieving quality heterogenous welds of P265 and Wr. N. 1.4541 steels required properties in repeated production cycle. Pro jadernou energetiku je tavné obloukové svařování jednou z klíčových technologií nejen pro výrobu zařízení, ale i pro jeho údržbu, montáž a opravy. Z toho důvodu, že uvnitř zařízení se nachází radioaktivní médium, jehož únik by mohl představovat katastrofické následky pro člověka i pro životní prostředí. Článek stručně představuje výsledky i zkušenosti z aplikace automatického orbitálního svařování. Cenným poznatkem je nejen odladění svařovacího postupu, ale také vymezení okrajových podmínek pro dosažení kvalitních heterogenních svarů ocelí P265GH a Wr. N. 1.4541 požadovaných vlastností v opakovaném cyklu výroby.

    image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/ Digital Library Univ...arrow_drop_down
    image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/
    Digital Library University of West Bohemia
    Other literature type . Article . 2020 . 2021 . Peer-reviewed
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      image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/ Digital Library Univ...arrow_drop_down
      image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/
      Digital Library University of West Bohemia
      Other literature type . Article . 2020 . 2021 . Peer-reviewed
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  • image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/
    Authors: Kostal, Michal; Losa, Evzen; Simakov, Stanislav; Schulc, Martin; +7 Authors

    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.

    image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/ arXiv.org e-Print Ar...arrow_drop_down
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    arXiv.org e-Print Archive
    Other literature type . Preprint . 2023
    image/svg+xml Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao Closed Access logo, derived from PLoS Open Access logo. This version with transparent background. http://commons.wikimedia.org/wiki/File:Closed_Access_logo_transparent.svg Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao
    Annals of Nuclear Energy
    Other literature type . Article . 2022 . Peer-reviewed
    License: Elsevier TDM
    https://doi.org/10.48550/arxiv...
    Article . 2023
    License: arXiv Non-Exclusive Distribution
    Data sources: Datacite
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      image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/ arXiv.org e-Print Ar...arrow_drop_down
      image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/
      arXiv.org e-Print Archive
      Other literature type . Preprint . 2023
      image/svg+xml Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao Closed Access logo, derived from PLoS Open Access logo. This version with transparent background. http://commons.wikimedia.org/wiki/File:Closed_Access_logo_transparent.svg Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao
      Annals of Nuclear Energy
      Other literature type . Article . 2022 . Peer-reviewed
      License: Elsevier TDM
      https://doi.org/10.48550/arxiv...
      Article . 2023
      License: arXiv Non-Exclusive Distribution
      Data sources: Datacite
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  • image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/
    Authors: Michal Kostal; Tomáš Czakoj; Petr Alexa; Jan Šimon; +10 Authors

    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 nuclear data in simulations thus, cross section validation is a key issue in any aims for refinement of any predictions. A small compact neutron generator is a promising tool for performing integral experiments and even for differential experiments. This paper deals with the measurement of the differential dosimetry cross sections using a small compact D-T neutron generator with 14.05 MeV neutron emission (10E8 n/s into 4pi). Achieving measurable activation at such a low flux field is allowed by using a larger amount of activation material placed in close measurement geometry during decay gamma measurement. The experimentally determined cross sections are in good agreement with the cross sections in the IRDFF-II dosimetry library. The comparison with other nuclear data libraries was performed as well. Its worth noting, the mean standard deviation in IRDFF-II library is about 4 %, while in case of other data libraries they are from 5.5 % - 7.5 %. This result can be understood as a validation of IRDFF-II using 14.05 MeV neutrons and also a confirmation of the applicability of small compact generators in the measurement of activation cross sections.

    image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/ arXiv.org e-Print Ar...arrow_drop_down
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    arXiv.org e-Print Archive
    Other literature type . Preprint . 2023
    image/svg+xml Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao Closed Access logo, derived from PLoS Open Access logo. This version with transparent background. http://commons.wikimedia.org/wiki/File:Closed_Access_logo_transparent.svg Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao
    Annals of Nuclear Energy
    Article . 2023 . Peer-reviewed
    License: Elsevier TDM
    Data sources: Sygma; Crossref
    https://doi.org/10.48550/arxiv...
    Article . 2023
    License: arXiv Non-Exclusive Distribution
    Data sources: Datacite
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      image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/ arXiv.org e-Print Ar...arrow_drop_down
      image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/
      arXiv.org e-Print Archive
      Other literature type . Preprint . 2023
      image/svg+xml Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao Closed Access logo, derived from PLoS Open Access logo. This version with transparent background. http://commons.wikimedia.org/wiki/File:Closed_Access_logo_transparent.svg Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao
      Annals of Nuclear Energy
      Article . 2023 . Peer-reviewed
      License: Elsevier TDM
      Data sources: Sygma; Crossref
      https://doi.org/10.48550/arxiv...
      Article . 2023
      License: arXiv Non-Exclusive Distribution
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  • image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/
    Authors: Cvešpr, Pavel;

    Information System LTOs solve issues of collection, processing and data evaluation from diagnostics, review and testing of energy equipment. These stored data are used for requirements of Ageing management of equipment and for support of preparation for Long Term Operation in the area of nuclear energetics. Aim of the article is to reveal new functionalities in mentioned SW which were developed on base of experience of end users and by its long age operating. Informační systém LTOs řeší problematiku sběru, zpracování a vyhodnocení dat z diagnostik, revizí a zkoušek energetických zařízení, které jsou využity pro sledování životnosti zařízení a pro podporu přípravy dlouhodobého provozu zejména v oblasti energetiky jaderné. Účelem příspěvku je představit nové funkčnosti tohoto systému vyvinuté na základě zkušeností koncových uživatelů s jeho dlouholetým užíváním.

    image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/ Digital Library Univ...arrow_drop_down
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    Digital Library University of West Bohemia
    Other literature type . Conference object . 2019 . 2023 . Peer-reviewed
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      image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/ Digital Library Univ...arrow_drop_down
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      Digital Library University of West Bohemia
      Other literature type . Conference object . 2019 . 2023 . Peer-reviewed
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    Authors: Peltan, Tomáš; Vilímová, Eva; Czakoj, Tomáš; Matěj, Zdeněk; +5 Authors

    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 wellcharacterised 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.

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    Digital Library University of West Bohemia
    Other literature type . Article . 2023 . Peer-reviewed
    image/svg+xml Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao Closed Access logo, derived from PLoS Open Access logo. This version with transparent background. http://commons.wikimedia.org/wiki/File:Closed_Access_logo_transparent.svg Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao
    Annals of Nuclear Energy
    Article . 2023 . Peer-reviewed
    License: Elsevier TDM
    Data sources: Crossref
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      image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/ Digital Library Univ...arrow_drop_down
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      Digital Library University of West Bohemia
      Other literature type . Article . 2023 . Peer-reviewed
      image/svg+xml Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao Closed Access logo, derived from PLoS Open Access logo. This version with transparent background. http://commons.wikimedia.org/wiki/File:Closed_Access_logo_transparent.svg Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao
      Annals of Nuclear Energy
      Article . 2023 . Peer-reviewed
      License: Elsevier TDM
      Data sources: Crossref
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    Authors: M. Lovecký; J. Závorka; J. Jiřičková; Z. Ondráček; +1 Authors

    Current designs of both large reactor units and small modular reactors utilize a nuclear fuel with increasing enrichment. This increasing demand for better nuclear fuel utilization is a challenge for nuclear fuel handling facilities. The operation with higher enriched fuels leads to reduced reserves to legislative and safety criticality limits of spent fuel transport, storage and final disposal facilities. Design changes in these facilities are restricted due to a boron content in steel and aluminum alloys that are limited by rolling, extrusion, welding and other manufacturing processes. One possible solution for spent fuel pools and casks is the burnup credit method that allows decreasing very high safety margins associated with the fresh fuel assumption in spent fuel facilities. This solution can be supplemented or replaced by an alternative solution based on placing the neutron absorber material directly into the fuel assembly, where its efficiency is higher than between fuel assemblies. A neutron absorber permanently fixed in guide tubes decreases system reactivity more efficiently than absorber sheets between the fuel assemblies. The paper summarizes possibilities of fixed neutron absorbers for various nuclear fuel and fuel handling facilities. Moreover, an absorber material was optimized to propose alternative options to boron. Multiple effective absorbers that do not require steel or aluminum alloy compatibility are discussed because fixed absorbers are placed inside zirconium or steel cladding.

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    Digital Library University of West Bohemia
    Other literature type . Article . 2023 . Peer-reviewed
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    Nuclear Engineering and Technology
    Article . 2023 . Peer-reviewed
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      Digital Library University of West Bohemia
      Other literature type . Article . 2023 . Peer-reviewed
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      Nuclear Engineering and Technology
      Article . 2023 . Peer-reviewed
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    Authors: Yee Van Fan; Jiří Jaromír Klemeš; Chew Tin Lee; Raymond R. Tan;

    There has been plenty of research on the influence of various socio-economic and demographic data on waste generation to develop effective and targeted waste reduction measures, including energy recovery. This study evaluates the relationship between the waste generation and Circular Material Use rate, Environmental Tax Revenue, and Global Innovation Index beyond the typical socio-economic factors (e.g., gross domestic product or population). Correlation analysis is conducted on the EU-27 datasets before the development of the predictive model. The correlation strength between the factors is discussed to identify the potential rebound effect from the central driver of economic growth and development. A positive correlation and partial rebound effect are identified in the data. The waste amount ending in disposal and energy recovery treatment increases with the Circular Material Use rate, suggesting that the expected gains from Circular Material Use rate are offset by other socio-economic factors such as increasing population or gross domestic product. However, a diminishing trend is observed in the rebound effect over the years. Multiple linear regression with validation is applied to identify the best fit model for predicting waste generation. Using population, gross domestic product, Circular Material Use rate, and Environmental Tax Revenues as independent variables, a model is generated with a mean absolute percentage error of 18.65% (7% lower than the benchmark) and R2 (coefficient of determination) of 0.995.

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    Energy Sources Part A Recovery Utilization and Environmental Effects
    Article . 2021 . Peer-reviewed
    License: CC BY NC ND
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      Energy Sources Part A Recovery Utilization and Environmental Effects
      Article . 2021 . Peer-reviewed
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    Authors: Závorka, Jiří; Lovecký, Martin; Jiřičková, Jana; Škoda, Radek;

    The presented paper describes experimental verification of the fixed neutron absorber for VVER-1000 fuel assemblies in the LR-0 zero-power reactor. This research determines the critical state parameters for fuel without these absorbers and for fuel with designed absorbers dedicated to the back-end of the fuel cycle and compares experimental data with the calculation. Several core configurations have been prepared, measured and evaluated. Two innovative forms of absorption materials were theoretically evaluated, then obtained and physically tested. From a neutronic and economic point of view, Gd2O3 and Sm2O3 in powder form were selected as absorber materials suitable for experimental verification. The reference calculation was realized with Serpent neutronic Monte Carlo code using ENDF/B nuclear data libraries.

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    Digital Library University of West Bohemia
    Other literature type . Article . 2023 . Peer-reviewed
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    Progress in Nuclear Energy
    Article . 2023 . Peer-reviewed
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    SSRN Electronic Journal
    Article . 2022 . Peer-reviewed
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      Digital Library University of West Bohemia
      Other literature type . Article . 2023 . Peer-reviewed
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      Progress in Nuclear Energy
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    Authors: Frk, Martin; Liedermann, Karel;

    V poslední době je stále větší důraz kladen na ekonomické souvislosti posuzování stavu a provozuschopnosti elektronických a elektrotechnických zařízení. Uplatňuje se diferencovaný přístup – v případech, kdy je diagnostika daného systému příliš nákladná v porovnání s náklady na výměnu, je nefunkční nebo i pouze nedostatečně spolehlivé zařízení vyměněno, zatímco naopak v případech, kdy jsou náklady spojené s výměnou či opravou stávajícího zařízení v porovnání s náklady na jeho diagnostiku příliš velké, preferují se diagnostika před výměnou. Tyto ekonomické zřetele se promítají do praktických aplikací mimo jiné v zařízeních pro jadernou energetiku, kdy je výměna určitého zařízení problematická či za normálního provozu téměř nemožná. V této práci jsou studovány dopady napěťového stárnutí na vlastnosti izolačního materiálu typu termikanit, který je určen pro vysokoteplotní aplikace, mimo jiné v izolacích elektrických strojů používaných v posuvu regulačních tyčí v jaderných reaktorech. Pro sledování změn v izolaci se nabízí dielektrická relaxační spektroskopie (DRS), tj. zjednodušeně měření závislosti obou složek komplexní permitivity zvoleného izolačního materiálu na frekvenci a teplotě. Vzhledem k tomu, že DRS je integrální metodou, která zaznamenává odezvu celého sledovaného materiálu jako celku, je otázkou, do jaké míry mohou být výsledky dielektrických měření schopné výpovědi o lokálních vlastnostech, které jsou pro elektrický průraz rozhodující. I při absenci bezprostřední korelace mezi dielektrickým spektrem a elektrickým průrazem však DRS poskytuje představu a informace o změnách probíhajících ve sledovaném materiálu v průběhu stárnutí.

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    Digital Library University of West Bohemia
    Other literature type . 2012 . 2020 . Peer-reviewed
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  • image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/
    Authors: Hussein Abdulkareem Saleh Abushamah; Ondřej Burian; Radek Škoda;

    Carbon-free thermally driven district cooling systems (DCS) can effectively mitigate the excessive electricity consumption and carbon emissions associated with the cooling sector. This study proposes a DCS that employs nuclear heat as the primary energy source. The system comprises three main subsystems: heat station, heat transmission, and cooling station. A heat-only small modular reactor called Teplator, gas boilers, and heat storage are considered to supply the heat required to drive absorption chillers; cold storage and compression chillers are the supplementary units. The technoeconomic aspects of the system are formulated, and an algorithm is developed to determine the optimal design and operation. The method is examined for supplying a typical cooling demand profile with a peak of 2050 MWc. The resulting optimized design includes 11 nuclear plants (150 MWt each), 20 000 MWth heat storage, and 1.9 m diameter heat supply/return pipes. Absorption chillers with a total capacity of 1424 MWc are determined, covering 92% of the total cooling demand, and 244 MWc of compression chillers and 20 000 MWch of cold storage are found to cover the peak and enhance the load following. This system saved 69% of the electricity consumption and carbon emissions and 34% of the costs compared with an electric-based scenario.

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    Digital Library University of West Bohemia
    Other literature type . Article . 2023 . Peer-reviewed
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      Digital Library University of West Bohemia
      Other literature type . Article . 2023 . Peer-reviewed
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    Authors: Vilcsek, Igor; Stach, Ondřej; Kříž, Antonín;

    For nuclear energy, fusion arc welding is one of the key technologies not only for production of equipment, but also for its maintenance, assembly and repair. Due to the fact that there is a radioactive medium inside the facility, the leakage of which could have catastrophic consequences for humans and the environment. The article briefly presents the results and experiences from the application of automatic orbital welding. A valuable finding is not only the debugging of the welding process, but also the definition of boundary conditions for achieving quality heterogenous welds of P265 and Wr. N. 1.4541 steels required properties in repeated production cycle. Pro jadernou energetiku je tavné obloukové svařování jednou z klíčových technologií nejen pro výrobu zařízení, ale i pro jeho údržbu, montáž a opravy. Z toho důvodu, že uvnitř zařízení se nachází radioaktivní médium, jehož únik by mohl představovat katastrofické následky pro člověka i pro životní prostředí. Článek stručně představuje výsledky i zkušenosti z aplikace automatického orbitálního svařování. Cenným poznatkem je nejen odladění svařovacího postupu, ale také vymezení okrajových podmínek pro dosažení kvalitních heterogenních svarů ocelí P265GH a Wr. N. 1.4541 požadovaných vlastností v opakovaném cyklu výroby.

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    Digital Library University of West Bohemia
    Other literature type . Article . 2020 . 2021 . Peer-reviewed
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      Digital Library University of West Bohemia
      Other literature type . Article . 2020 . 2021 . Peer-reviewed
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    Authors: Kostal, Michal; Losa, Evzen; Simakov, Stanislav; Schulc, Martin; +7 Authors

    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.

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    arXiv.org e-Print Archive
    Other literature type . Preprint . 2023
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    Annals of Nuclear Energy
    Other literature type . Article . 2022 . Peer-reviewed
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    https://doi.org/10.48550/arxiv...
    Article . 2023
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      arXiv.org e-Print Archive
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      Annals of Nuclear Energy
      Other literature type . Article . 2022 . Peer-reviewed
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    Authors: Michal Kostal; Tomáš Czakoj; Petr Alexa; Jan Šimon; +10 Authors

    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 nuclear data in simulations thus, cross section validation is a key issue in any aims for refinement of any predictions. A small compact neutron generator is a promising tool for performing integral experiments and even for differential experiments. This paper deals with the measurement of the differential dosimetry cross sections using a small compact D-T neutron generator with 14.05 MeV neutron emission (10E8 n/s into 4pi). Achieving measurable activation at such a low flux field is allowed by using a larger amount of activation material placed in close measurement geometry during decay gamma measurement. The experimentally determined cross sections are in good agreement with the cross sections in the IRDFF-II dosimetry library. The comparison with other nuclear data libraries was performed as well. Its worth noting, the mean standard deviation in IRDFF-II library is about 4 %, while in case of other data libraries they are from 5.5 % - 7.5 %. This result can be understood as a validation of IRDFF-II using 14.05 MeV neutrons and also a confirmation of the applicability of small compact generators in the measurement of activation cross sections.

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    arXiv.org e-Print Archive
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    Annals of Nuclear Energy
    Article . 2023 . Peer-reviewed
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      Annals of Nuclear Energy
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    Authors: Cvešpr, Pavel;

    Information System LTOs solve issues of collection, processing and data evaluation from diagnostics, review and testing of energy equipment. These stored data are used for requirements of Ageing management of equipment and for support of preparation for Long Term Operation in the area of nuclear energetics. Aim of the article is to reveal new functionalities in mentioned SW which were developed on base of experience of end users and by its long age operating. Informační systém LTOs řeší problematiku sběru, zpracování a vyhodnocení dat z diagnostik, revizí a zkoušek energetických zařízení, které jsou využity pro sledování životnosti zařízení a pro podporu přípravy dlouhodobého provozu zejména v oblasti energetiky jaderné. Účelem příspěvku je představit nové funkčnosti tohoto systému vyvinuté na základě zkušeností koncových uživatelů s jeho dlouholetým užíváním.

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    Digital Library University of West Bohemia
    Other literature type . Conference object . 2019 . 2023 . Peer-reviewed
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      Digital Library University of West Bohemia
      Other literature type . Conference object . 2019 . 2023 . Peer-reviewed
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    Authors: Peltan, Tomáš; Vilímová, Eva; Czakoj, Tomáš; Matěj, Zdeněk; +5 Authors

    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 wellcharacterised 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.

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    Digital Library University of West Bohemia
    Other literature type . Article . 2023 . Peer-reviewed
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    Annals of Nuclear Energy
    Article . 2023 . Peer-reviewed
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      Digital Library University of West Bohemia
      Other literature type . Article . 2023 . Peer-reviewed
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      Annals of Nuclear Energy
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    Authors: M. Lovecký; J. Závorka; J. Jiřičková; Z. Ondráček; +1 Authors

    Current designs of both large reactor units and small modular reactors utilize a nuclear fuel with increasing enrichment. This increasing demand for better nuclear fuel utilization is a challenge for nuclear fuel handling facilities. The operation with higher enriched fuels leads to reduced reserves to legislative and safety criticality limits of spent fuel transport, storage and final disposal facilities. Design changes in these facilities are restricted due to a boron content in steel and aluminum alloys that are limited by rolling, extrusion, welding and other manufacturing processes. One possible solution for spent fuel pools and casks is the burnup credit method that allows decreasing very high safety margins associated with the fresh fuel assumption in spent fuel facilities. This solution can be supplemented or replaced by an alternative solution based on placing the neutron absorber material directly into the fuel assembly, where its efficiency is higher than between fuel assemblies. A neutron absorber permanently fixed in guide tubes decreases system reactivity more efficiently than absorber sheets between the fuel assemblies. The paper summarizes possibilities of fixed neutron absorbers for various nuclear fuel and fuel handling facilities. Moreover, an absorber material was optimized to propose alternative options to boron. Multiple effective absorbers that do not require steel or aluminum alloy compatibility are discussed because fixed absorbers are placed inside zirconium or steel cladding.

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    Digital Library University of West Bohemia
    Other literature type . Article . 2023 . Peer-reviewed
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    Nuclear Engineering and Technology
    Article . 2023 . Peer-reviewed
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      Digital Library University of West Bohemia
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      Nuclear Engineering and Technology
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    Authors: Yee Van Fan; Jiří Jaromír Klemeš; Chew Tin Lee; Raymond R. Tan;

    There has been plenty of research on the influence of various socio-economic and demographic data on waste generation to develop effective and targeted waste reduction measures, including energy recovery. This study evaluates the relationship between the waste generation and Circular Material Use rate, Environmental Tax Revenue, and Global Innovation Index beyond the typical socio-economic factors (e.g., gross domestic product or population). Correlation analysis is conducted on the EU-27 datasets before the development of the predictive model. The correlation strength between the factors is discussed to identify the potential rebound effect from the central driver of economic growth and development. A positive correlation and partial rebound effect are identified in the data. The waste amount ending in disposal and energy recovery treatment increases with the Circular Material Use rate, suggesting that the expected gains from Circular Material Use rate are offset by other socio-economic factors such as increasing population or gross domestic product. However, a diminishing trend is observed in the rebound effect over the years. Multiple linear regression with validation is applied to identify the best fit model for predicting waste generation. Using population, gross domestic product, Circular Material Use rate, and Environmental Tax Revenues as independent variables, a model is generated with a mean absolute percentage error of 18.65% (7% lower than the benchmark) and R2 (coefficient of determination) of 0.995.

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    Other literature type . 2021
    License: CC BY
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    Other literature type . 2021
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    Energy Sources Part A Recovery Utilization and Environmental Effects
    Article . 2021 . Peer-reviewed
    License: CC BY NC ND
    Data sources: Crossref
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      Other literature type . 2021
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      Energy Sources Part A Recovery Utilization and Environmental Effects
      Article . 2021 . Peer-reviewed
      License: CC BY NC ND
      Data sources: Crossref
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    Authors: Závorka, Jiří; Lovecký, Martin; Jiřičková, Jana; Škoda, Radek;

    The presented paper describes experimental verification of the fixed neutron absorber for VVER-1000 fuel assemblies in the LR-0 zero-power reactor. This research determines the critical state parameters for fuel without these absorbers and for fuel with designed absorbers dedicated to the back-end of the fuel cycle and compares experimental data with the calculation. Several core configurations have been prepared, measured and evaluated. Two innovative forms of absorption materials were theoretically evaluated, then obtained and physically tested. From a neutronic and economic point of view, Gd2O3 and Sm2O3 in powder form were selected as absorber materials suitable for experimental verification. The reference calculation was realized with Serpent neutronic Monte Carlo code using ENDF/B nuclear data libraries.

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    Digital Library University of West Bohemia
    Other literature type . Article . 2023 . Peer-reviewed
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    Progress in Nuclear Energy
    Article . 2023 . Peer-reviewed
    License: Elsevier TDM
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    SSRN Electronic Journal
    Article . 2022 . Peer-reviewed
    Data sources: Crossref
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      Digital Library University of West Bohemia
      Other literature type . Article . 2023 . Peer-reviewed
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      Progress in Nuclear Energy
      Article . 2023 . Peer-reviewed
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      Article . 2022 . Peer-reviewed
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    Authors: Frk, Martin; Liedermann, Karel;

    V poslední době je stále větší důraz kladen na ekonomické souvislosti posuzování stavu a provozuschopnosti elektronických a elektrotechnických zařízení. Uplatňuje se diferencovaný přístup – v případech, kdy je diagnostika daného systému příliš nákladná v porovnání s náklady na výměnu, je nefunkční nebo i pouze nedostatečně spolehlivé zařízení vyměněno, zatímco naopak v případech, kdy jsou náklady spojené s výměnou či opravou stávajícího zařízení v porovnání s náklady na jeho diagnostiku příliš velké, preferují se diagnostika před výměnou. Tyto ekonomické zřetele se promítají do praktických aplikací mimo jiné v zařízeních pro jadernou energetiku, kdy je výměna určitého zařízení problematická či za normálního provozu téměř nemožná. V této práci jsou studovány dopady napěťového stárnutí na vlastnosti izolačního materiálu typu termikanit, který je určen pro vysokoteplotní aplikace, mimo jiné v izolacích elektrických strojů používaných v posuvu regulačních tyčí v jaderných reaktorech. Pro sledování změn v izolaci se nabízí dielektrická relaxační spektroskopie (DRS), tj. zjednodušeně měření závislosti obou složek komplexní permitivity zvoleného izolačního materiálu na frekvenci a teplotě. Vzhledem k tomu, že DRS je integrální metodou, která zaznamenává odezvu celého sledovaného materiálu jako celku, je otázkou, do jaké míry mohou být výsledky dielektrických měření schopné výpovědi o lokálních vlastnostech, které jsou pro elektrický průraz rozhodující. I při absenci bezprostřední korelace mezi dielektrickým spektrem a elektrickým průrazem však DRS poskytuje představu a informace o změnách probíhajících ve sledovaném materiálu v průběhu stárnutí.

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    image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/
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    Digital Library University of West Bohemia
    Other literature type . 2012 . 2020 . Peer-reviewed
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      Digital Library University of West Bohemia
      Other literature type . 2012 . 2020 . Peer-reviewed
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