Review of the primary coolant chemistry at NPP Temelín and its impact on the fuel cladding

Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F11%3A%230000672" target="_blank" >RIV/26722445:_____/11:#0000672 - isvavai.cz</a>
Result on the web
<a href="http://wwerfuel2011.inrne.bas.bg/" target="_blank" >http://wwerfuel2011.inrne.bas.bg/</a>
DOI - Digital Object Identifier
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Result language
angličtina
Original language name
Review of the primary coolant chemistry at NPP Temelín and its impact on the fuel cladding
Original language description
One of the main goals in Research Centre Řež Ltd, in the department of Research Reactors is the study of the VVER, PWR and BWR primary coolant chemistry impact on the construct materials in the whole primary system. Reliability of nuclear fuel and radiation fields surrounding primary systems as well, are important aspects of overall nuclear reactor safety. With the use of research reactor LVR-15 and several experimental loops and devices Research Centre Řež is participating on the recommendations for all NPPs in Czech Republic (VVER-440 in Dukovany, VVER-1000 in Temelín) in the mentioned problematic. NPP Temelín is a first VVER reactor, where the Russian reactor design meets the American fuel design. Since 2009, Research Centre Řež is also participating on the post irradiation inspection program at NPP Temelín. Together with the previous fuel vendor Westinghouse Electric Company LLC, Research Centre Řež is performing independent support for the fuel inspection and repair. During these
Czech name
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Czech description
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Project
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Continuities
I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Publication year
2011
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

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