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Neutron flux measurement and calculation behind wer-1000 reactor pressure vessel simulator placed in LR-0 reactor

The result's identifiers

  • Result code in IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F60162694%3AG43__%2F15%3A00532026" target="_blank" >RIV/60162694:G43__/15:00532026 - isvavai.cz</a>

  • Result on the web

    <a href="http://vavtest.unob.cz/registr" target="_blank" >http://vavtest.unob.cz/registr</a>

  • DOI - Digital Object Identifier

Alternative languages

  • Result language

    angličtina

  • Original language name

    Neutron flux measurement and calculation behind wer-1000 reactor pressure vessel simulator placed in LR-0 reactor

  • Original language description

    The neutron fluence in the reactor pressure vessel is an important physical quantity affecting material degradation, which reflects in the vessel residual lifetime. The measured fluxes are normalized per InA of monitor current, which corresponds to 0.01 W of thermal power, or 3.631E8 fiss/s. The scaling factor for such evaluation was determined from neutron flux in reference position, evaluated by means of reaction rate in well defined activation detector. This scaling factor was verified by means of gamma spectroscopy of irradiated fuel. This independent method is based on the proportionality between the net peak area (NPA) of selected fission product and released energy. 92Sr fission product is used on the LR-0 reactor due to its suitable values of gamma energies with no parasitic peaks and half-life allowing reasonable manipulation time after irradiation. 92Sr has also no coincidence photons with measurable activity after defined irradiation conditions and it has also little difference between the theoretical and measured decay. Both neutron and photon transport calculations were performed with the MCNPX 2.6.0 code with different nuclear data libraries. The fast fluxes behind the reactor pressure vessel (RPV) simulator were calculated using fixed source model with defined (calculated by MCNPX) power density across core. The results clearly show the distinguishable dependency of nuclear data libraries on the results. The effect of different libraries is mostly notable in the fluxes over 5 MeV, where the JENDL 4 results overestimate experiment by 46 %, while JEFF 3.1 by 9.5 %.

  • Czech name

  • Czech description

Classification

  • Type

    D - Article in proceedings

  • CEP classification

    JF - Nuclear energy

  • OECD FORD branch

Result continuities

  • Project

  • 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

  • Article name in the collection

    Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference (M&C+SNA+MC 2015)

  • ISBN

    978-1-5108-0804-1

  • ISSN

  • e-ISSN

  • Number of pages

    11

  • Pages from-to

    3102-3112

  • Publisher name

    American Nuclear Society ( ANS )

  • Place of publication

    La Grange Park, IL, USA

  • Event location

    Nashville, Tennessee, USA

  • Event date

    Apr 19, 2015

  • Type of event by nationality

    WRD - Celosvětová akce

  • UT code for WoS article