On the effect of the core boundary power distribution on the radiation situation in reactor components

Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F24%3AN0000141" target="_blank" >RIV/26722445:_____/24:N0000141 - isvavai.cz</a>
Result on the web
<a href="https://www.epj-conferences.org/articles/epjconf/abs/2024/18/epjconf_isrd-17_01006/epjconf_isrd-17_01006.html" target="_blank" >https://www.epj-conferences.org/articles/epjconf/abs/2024/18/epjconf_isrd-17_01006/epjconf_isrd-17_01006.html</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1051/epjconf/202430801006" target="_blank" >10.1051/epjconf/202430801006</a>

Result language
angličtina
Original language name
On the effect of the core boundary power distribution on the radiation situation in reactor components
Original language description
The assessment of the neutron flux distribution in nuclear power plant components, like reactor internals and the pressure vessel, is one of the most important parts of their residual lifetime evaluation process because the irradiation damage of these components is strongly dependent on it. The fast neutron fluences in power reactors are generally determined using calculations and verified by measurements. Discrepancies between them sometimes occur, which can be caused by be the inaccuracies in the power distribution used in neutron transport calculations. This paper quantifies the effect of uncertainty in power density on the neutron fluences behind the reactor pressure vessel (RPV). An increase in power density was experimentally simulated by implementing a higher uranium enrichment of certain selected pins. The experiment was also simulated using the MCNP code with the ENDF/B-VII.1 library. Both the experimental and calculational data show a significant local increase in neutron flux. Even behind the RPV, the increase is as high as 25%, while the local power increase in the perturbed pins is about 70–80%, which is approximately equal to the 2 σ power density uncertainties. A good agreement between measurement and calculation was found.
Czech name
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Czech description
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Type
D - Article in proceedings
CEP classification
—
OECD FORD branch
20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Publication year
2024
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

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