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Possibility of implementation of 6-year fuel cycle at NPP with VVER-440 reactor

The result's identifiers

  • Result code in IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F15%3A00237186" target="_blank" >RIV/68407700:21340/15:00237186 - isvavai.cz</a>

  • Alternative codes found

    RIV/46356088:_____/15:#0001710

  • Result on the web

    <a href="http://dx.doi.org/10.1016/j.nucengdes.2015.08.024" target="_blank" >http://dx.doi.org/10.1016/j.nucengdes.2015.08.024</a>

  • DOI - Digital Object Identifier

    <a href="http://dx.doi.org/10.1016/j.nucengdes.2015.08.024" target="_blank" >10.1016/j.nucengdes.2015.08.024</a>

Alternative languages

  • Result language

    angličtina

  • Original language name

    Possibility of implementation of 6-year fuel cycle at NPP with VVER-440 reactor

  • Original language description

    This paper discusses possibility of an extension of a fuel cycle at a VVER-440 reactor for up to 6 years. The prolongation of a fuel cycle was realized by optimization of a fuel design and increasing of a fuel enrichment. The modified design of the fuelassembly covers change of pellet geometry, decreasing of parasitic absorption in construction materials, improved moderation of fuel pins and also increase of enrichment. Fuel assemblies with enrichment up to 7% U-235 are considered for prolonged fuel batches. Three different batch lengths were considered for evaluation of core properties - 12,18 and 24 months, and two types of burnable absorbers were included - Gd2O3 and Er2O3. Comparison of proposed fuel assemblies was realized by length of a batch, average burnup, maximal power of fuel assembly or fuel pin, control fuel assembly worth, reactivity coefficients, and effective delayed neutrons fraction. Comparison of characteristics of a burned fuel discharged from a reactor core is dis

  • Czech name

  • Czech description

Classification

  • Type

    J<sub>x</sub> - Unclassified - Peer-reviewed scientific article (Jimp, Jsc and Jost)

  • CEP classification

    JF - Nuclear energy

  • OECD FORD branch

Result continuities

  • Project

    <a href="/en/project/TE01020455" target="_blank" >TE01020455: Centre for Advanced Nuclear Technologies (CANUT)</a><br>

  • Continuities

    I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Others

  • Publication year

    2015

  • 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

  • Volume of the periodical

    295

  • Issue of the periodical within the volume

    Dec

  • Country of publishing house

    NL - THE KINGDOM OF THE NETHERLANDS

  • Number of pages

    8

  • Pages from-to

    40-47

  • UT code for WoS article

    000367413700004

  • EID of the result in the Scopus database

    2-s2.0-84945179250