The Effect of Iron Cross-Section in Thermal Region on Neutron Transport in VVER-1000 Mock-Up In LR-0 Reactor

Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F16%3AN0000059" target="_blank" >RIV/26722445:_____/16:N0000059 - isvavai.cz</a>
Alternative codes found
RIV/26722445:_____/17:N0000040
Result on the web
<a href="http://dx.doi.org/10.1115/1.4034568" target="_blank" >http://dx.doi.org/10.1115/1.4034568</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1115/1.4034568" target="_blank" >10.1115/1.4034568</a>

Result language
angličtina
Original language name
The Effect of Iron Cross-Section in Thermal Region on Neutron Transport in VVER-1000 Mock-Up In LR-0 Reactor
Original language description
The iron cross-section description in thermal region influences the thermal neutron flux prediction in steel structural components of reactor, and also in regions adjoining them. In fuel the thermal neutron flux level is proportional to pin power density. This quantity is important criterion reflected in limits and conditions of reactor operation. The new power density evaluation shows notable, well distinguishable discrepancies between calculation realized using CENDL-3.1 nuclear data library and experimentally determined pin power density in boundary row of pins. All experiments were carried out in VVER-1000 transport Mock-UP placed in LR-0 reactor.
Czech name
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Czech description
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Type
J<sub>x</sub> - Unclassified - Peer-reviewed scientific article (Jimp, Jsc and Jost)
CEP classification
JF - Nuclear energy
OECD FORD branch
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Project
Result was created during the realization of more than one project. More information in the Projects tab.
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Publication year
2016
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

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