Usage of Thorium Based Nuclear Fuel in VVER reactors

Kód výsledku v 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>

Výsledek na webu

—

DOI - Digital Object Identifier

—

Jazyk výsledku

angličtina

Název v původním jazyce

Usage of Thorium Based Nuclear Fuel in VVER reactors

Popis výsledku v původním jazyce

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.

Název v anglickém jazyce

Usage of Thorium Based Nuclear Fuel in VVER reactors

Popis výsledku anglicky

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.

Druh

D - Stať ve sborníku

CEP obor

JF - Jaderná energetika

OECD FORD obor

—

Projekt

—

Návaznosti

Z - Vyzkumny zamer (s odkazem do CEZ)

Rok uplatnění

2010

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Název statě ve sborníku

Proceedings of the 2010 International Congress on Advances in Nuclear Power Plants (ICAPP '10)

ISBN

978-1-61738-643-5

ISSN

—

e-ISSN

—

Počet stran výsledku

9

Strana od-do

2000-2008

Název nakladatele

American Nuclear Society

Místo vydání

LaGrange Park, Ilinois

Místo konání akce

San Diego

Datum konání akce

13. 6. 2010

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

—