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Burnable absorber layer in HTR coated particles for OTTO fuel cycle

Identifikátory výsledku

  • Kód výsledku v IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F49777513%3A23220%2F18%3A43953837" target="_blank" >RIV/49777513:23220/18:43953837 - isvavai.cz</a>

  • Výsledek na webu

  • DOI - Digital Object Identifier

Alternativní jazyky

  • Jazyk výsledku

    angličtina

  • Název v původním jazyce

    Burnable absorber layer in HTR coated particles for OTTO fuel cycle

  • Popis výsledku v původním jazyce

    High temperature reactor is loaded by fuel pebbles that slowly flow through the reactor core. Reactor operation is described by a continuous on-power refueling with two possible fuel cycles. Multi-pass scheme allows lower peak power density. Moreover, multiple passing through the core shifts power peak into central parts of the core. On the other hand, multi-pass scheme requires complicated refueling machine. Single-passing scheme known as OTTO cycle (Once-Through-Then-Out) avoids refueling machine with the disadvantage of high peak power density located at the top of the core. There are few paths for diminishing and shifting of the power peak - non-cylindrical core shapes, absorbing reflectors, thorium fuel, radial fuel zoning and burnable absorbers. From construction point of view, burnable absorbers are the first choice. In contrast to LWR reactors, HTR reactor is randomly filled by hundred thousand fuel assemblies (pebbles), each fuel pebble contains thousands of coated particles stochastically embedded in the graphite matrix. Because of this double heterogeneity, fuel design studies should be based on both fuel assembly level as well as core level calculations. Standard LWR burnable absorber materials gadolinium, boron and erbium were analyzed for HTR, however, other materials are proposed for specific HTR conditions, mainly very high fuel discharge burnup. Coated layer created by burnable absorber is small, therefore, thermal and chemical compatibility with UO2 matrix is not needed and the choice of optimum material can be more focused on neutronics analysis. Monte Carlo approach with Serpent 2 code is used because of a specific random walk implementation that is distinctively faster than the standard ray tracing methods.

  • Název v anglickém jazyce

    Burnable absorber layer in HTR coated particles for OTTO fuel cycle

  • Popis výsledku anglicky

    High temperature reactor is loaded by fuel pebbles that slowly flow through the reactor core. Reactor operation is described by a continuous on-power refueling with two possible fuel cycles. Multi-pass scheme allows lower peak power density. Moreover, multiple passing through the core shifts power peak into central parts of the core. On the other hand, multi-pass scheme requires complicated refueling machine. Single-passing scheme known as OTTO cycle (Once-Through-Then-Out) avoids refueling machine with the disadvantage of high peak power density located at the top of the core. There are few paths for diminishing and shifting of the power peak - non-cylindrical core shapes, absorbing reflectors, thorium fuel, radial fuel zoning and burnable absorbers. From construction point of view, burnable absorbers are the first choice. In contrast to LWR reactors, HTR reactor is randomly filled by hundred thousand fuel assemblies (pebbles), each fuel pebble contains thousands of coated particles stochastically embedded in the graphite matrix. Because of this double heterogeneity, fuel design studies should be based on both fuel assembly level as well as core level calculations. Standard LWR burnable absorber materials gadolinium, boron and erbium were analyzed for HTR, however, other materials are proposed for specific HTR conditions, mainly very high fuel discharge burnup. Coated layer created by burnable absorber is small, therefore, thermal and chemical compatibility with UO2 matrix is not needed and the choice of optimum material can be more focused on neutronics analysis. Monte Carlo approach with Serpent 2 code is used because of a specific random walk implementation that is distinctively faster than the standard ray tracing methods.

Klasifikace

  • Druh

    D - Stať ve sborníku

  • CEP obor

  • OECD FORD obor

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

Návaznosti výsledku

  • Projekt

    <a href="/cs/project/TE01020455" target="_blank" >TE01020455: Centrum pokročilých jaderných technologií (CANUT)</a><br>

  • Návaznosti

    P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Ostatní

  • Rok uplatnění

    2018

  • Kód důvěrnosti údajů

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

Údaje specifické pro druh výsledku

  • Název statě ve sborníku

    Proceedings : 27th International Conference Nuclear Energy for New Europe (NENE 2018)

  • ISBN

    978-961-6207-45-4

  • ISSN

  • e-ISSN

    neuvedeno

  • Počet stran výsledku

    8

  • Strana od-do

    "214.1"-"214.8"

  • Název nakladatele

    Nuclear Society of Slovenia

  • Místo vydání

    Ljubljana

  • Místo konání akce

    Portorož, Slovenia

  • Datum konání akce

    10. 9. 2018

  • Typ akce podle státní příslušnosti

    WRD - Celosvětová akce

  • Kód UT WoS článku