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Neutronic performance of VVER-1200 reactor with advanced fuel and cladding materials

The result's identifiers

  • Result code in IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F23%3A00364156" target="_blank" >RIV/68407700:21340/23:00364156 - isvavai.cz</a>

  • Result on the web

    <a href="https://doi.org/10.1016/j.nucengdes.2023.112216" target="_blank" >https://doi.org/10.1016/j.nucengdes.2023.112216</a>

  • DOI - Digital Object Identifier

    <a href="http://dx.doi.org/10.1016/j.nucengdes.2023.112216" target="_blank" >10.1016/j.nucengdes.2023.112216</a>

Alternative languages

  • Result language

    angličtina

  • Original language name

    Neutronic performance of VVER-1200 reactor with advanced fuel and cladding materials

  • Original language description

    Nuclear reactor operation and safety are connected with a nuclear fuel design and its material and geometry properties. An increase in nuclear safety is therefore based on a neutronic and thermal analysis of the materials used in a core. This paper analyzes neutronic properties of a VVER-1200 fuel assembly with alternate fuel and cladding materials that consider Accident Tolerant or Advanced Technology Fuels (ATF). The ATF nuclear fuel development started with the post-Fukushima efforts and its main purpose is a reduction of the high-temperature hydrogen production from the zirconium water reaction. Five ATF cladding candidates with reference Zr-based alloy are studied in this paper as well as six ATF fuel candidates together with an additional standard UO2 reference case. The results are analysed based on the multiplication characteristics, reactivity feedbacks, and spent nuclear fuel composition.

  • Czech name

  • Czech description

Classification

  • Type

    J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database

  • CEP classification

  • OECD FORD branch

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

Result continuities

  • Project

    <a href="/en/project/TK03020034" target="_blank" >TK03020034: Utilization of Advanced Materials for New Types of Nuclear Fuels</a><br>

  • Continuities

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

Others

  • Publication year

    2023

  • Confidentiality

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

Data specific for result type

  • Name of the periodical

    Nuclear Engineering and Design

  • ISSN

    0029-5493

  • e-ISSN

    1872-759X

  • Volume of the periodical

    405

  • Issue of the periodical within the volume

    04

  • Country of publishing house

    NL - THE KINGDOM OF THE NETHERLANDS

  • Number of pages

    11

  • Pages from-to

  • UT code for WoS article

    000942085400001

  • EID of the result in the Scopus database

    2-s2.0-85148003488