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Influence of mixed core in the radionuclides releases and hydrogen production for VVER-1000

Identifikátory výsledku

  • Kód výsledku v IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F86652052%3A_____%2F24%3AN0000007" target="_blank" >RIV/86652052:_____/24:N0000007 - isvavai.cz</a>

  • Výsledek na webu

    <a href="https://www.sciencedirect.com/science/article/pii/S0029549323007070" target="_blank" >https://www.sciencedirect.com/science/article/pii/S0029549323007070</a>

  • DOI - Digital Object Identifier

    <a href="http://dx.doi.org/10.1016/j.nucengdes.2023.112858" target="_blank" >10.1016/j.nucengdes.2023.112858</a>

Alternativní jazyky

  • Jazyk výsledku

    angličtina

  • Název v původním jazyce

    Influence of mixed core in the radionuclides releases and hydrogen production for VVER-1000

  • Popis výsledku v původním jazyce

    This paper aims to compare the behaviour of VVER-1000 Nuclear Power Plants (NPPs) under DEC-A/B conditions, contemplating different fuel assemblies considered in mixed cores. The main characteristics of both fuel assemblies are described in this paper, with a focus on highlighting the key differences in mass composition. There are three models under consideration: Model A, Model B and Model C. Model A consists of a core entirely filled with fuel assemblies equipped with grids made of Zr-1 %Nb, referred to as “Type A” through the paper. Model B comprises a core filled with fuel assemblies that have grids made of Alloy 718 (aka Inconel), referred to “Type B”. Lastly, Model C features a mixed core of 151 fuel assemblies with Zr-1 %Nb grids and 12 fuel assemblies with Inconel grids. Initially, the primary distinctions between these fuel assemblies types are the number and composition of their spacer grids. Type A fuel assemblies have 13 grids made of Zirconium, while Type B fuel assemblies have 16 grids made of Inconel. It was initially anticipated that the reduction in the mass of zirconium available for oxidation would lead to lower hydrogen production in Model B compared to Model A. However, it was observed that the Inconel grids in Type B fuel assemblies provide enhanced structural support, prolonging the oxidation reaction and yielding more hydrogen during the initial oxidation phase compared to Type A fuel assemblies. Moving on to the mixed core configuration (Model C), the Inconel grids in Type B fuel assembly also offer superior structural support. This results in an extended oxidation process. The Type A fuel assemblies having a significant zirconium mass, oxidation in intensified, causing a rise in temperature due the exothermic reaction and leading to the producing of a greater amount of hydrogen compared to the other two models. This pattern is also observed in radionuclide releases. In conclusion, this study sheds light on the behaviour of VVER-1000 NPPs under DEC-A/B conditions, considering different fuel assembly types and mixed core configurations. The results indicate that the choice of grid materials significantly influences the oxidation process and hydrogen production, with Inconel grids exhibiting extended oxidation and hydrogen generation behaviour in both pure and mixed core setups.

  • Název v anglickém jazyce

    Influence of mixed core in the radionuclides releases and hydrogen production for VVER-1000

  • Popis výsledku anglicky

    This paper aims to compare the behaviour of VVER-1000 Nuclear Power Plants (NPPs) under DEC-A/B conditions, contemplating different fuel assemblies considered in mixed cores. The main characteristics of both fuel assemblies are described in this paper, with a focus on highlighting the key differences in mass composition. There are three models under consideration: Model A, Model B and Model C. Model A consists of a core entirely filled with fuel assemblies equipped with grids made of Zr-1 %Nb, referred to as “Type A” through the paper. Model B comprises a core filled with fuel assemblies that have grids made of Alloy 718 (aka Inconel), referred to “Type B”. Lastly, Model C features a mixed core of 151 fuel assemblies with Zr-1 %Nb grids and 12 fuel assemblies with Inconel grids. Initially, the primary distinctions between these fuel assemblies types are the number and composition of their spacer grids. Type A fuel assemblies have 13 grids made of Zirconium, while Type B fuel assemblies have 16 grids made of Inconel. It was initially anticipated that the reduction in the mass of zirconium available for oxidation would lead to lower hydrogen production in Model B compared to Model A. However, it was observed that the Inconel grids in Type B fuel assemblies provide enhanced structural support, prolonging the oxidation reaction and yielding more hydrogen during the initial oxidation phase compared to Type A fuel assemblies. Moving on to the mixed core configuration (Model C), the Inconel grids in Type B fuel assembly also offer superior structural support. This results in an extended oxidation process. The Type A fuel assemblies having a significant zirconium mass, oxidation in intensified, causing a rise in temperature due the exothermic reaction and leading to the producing of a greater amount of hydrogen compared to the other two models. This pattern is also observed in radionuclide releases. In conclusion, this study sheds light on the behaviour of VVER-1000 NPPs under DEC-A/B conditions, considering different fuel assembly types and mixed core configurations. The results indicate that the choice of grid materials significantly influences the oxidation process and hydrogen production, with Inconel grids exhibiting extended oxidation and hydrogen generation behaviour in both pure and mixed core setups.

Klasifikace

  • Druh

    J<sub>imp</sub> - Článek v periodiku v databázi Web of Science

  • CEP obor

  • OECD FORD obor

    20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Návaznosti výsledku

  • Projekt

  • Návaznosti

    I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Ostatní

  • Rok uplatnění

    2024

  • Kód důvěrnosti údajů

    S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Údaje specifické pro druh výsledku

  • Název periodika

    Nuclear Engineering and Design

  • ISSN

    0029-5493

  • e-ISSN

    1872-759X

  • Svazek periodika

    417

  • Číslo periodika v rámci svazku

    February

  • Stát vydavatele periodika

    CH - Švýcarská konfederace

  • Počet stran výsledku

    16

  • Strana od-do

    112858

  • Kód UT WoS článku

    001147840900001

  • EID výsledku v databázi Scopus

    2-s2.0-85180536167