Usage of Thorium Based Nuclear Fuel in VVER reactors

Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F10%3A00180332" target="_blank" >RIV/68407700:21340/10:00180332 - isvavai.cz</a>
Result on the web
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DOI - Digital Object Identifier
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Result language
angličtina
Original language name
Usage of Thorium Based Nuclear Fuel in VVER reactors
Original language description
Thorium is an alternative fertile material which can be used in various types of nuclear reactors. We investigate the possibility to utilize thorium fuel cycle in the current generation of the Russian design VVER-1000 reactor. We focus especially on advantages thorium could bring if implemented in the frame of the current fuel assembly design, so that the thorium based assemblies would be a direct replacement of current uranium fuel assemblies. Three thorium-bearing assembly types were investigated. They differ in material which acts as a fissile support: Pu recovered from spent fuel, low enriched uranium and 233U recovered from previous thorium irradiation were considered. These assemblies were designed in such a way that they could be loaded in a standard 5-year fuel cycle. Calculations were carried out in HELIOS lattice code combined with 3D nodal code ANDREA.
Czech name
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Czech description
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Publication year
2010
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Article name in the collection
Proceedings of the 2010 International Congress on Advances in Nuclear Power Plants (ICAPP '10)
ISBN
978-1-61738-643-5
ISSN
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e-ISSN
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Number of pages
9
Pages from-to
2000-2008
Publisher name
American Nuclear Society
Place of publication
LaGrange Park, Ilinois
Event location
San Diego
Event date
Jun 13, 2010
Type of event by nationality
WRD - Celosvětová akce
UT code for WoS article
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