Progress in Thorium Fuel Cycle Technology Devoted to Molten Salt Reactor System

Result code in IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F15%3A%230001143" target="_blank" >RIV/26722445:_____/15:#0001143 - 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

Progress in Thorium Fuel Cycle Technology Devoted to Molten Salt Reactor System

Original language description

Molten Salt Reactor (MSR) is the only Generation IV reactor system which can be effectively operated as a breeder within the thorium – uranium fuel cycle (232Th – 233U) with the breeding factor significantly higher than one. This ability results from liquid fuel on-line reprocessing, which enables extraction of originated uranium 233U or its precursor 233Pa respectively. A combination of liquid fuel and thorium – uranium cycle exhibit also other significant advantages of MSR system - minimized production of higher transuranium elements and low fission products inventory, minimal excess of reactivity and high power density of the reactor. Whereas the basic MSR reactor design and operation were successfully verified in 1960s during the MSRE project, the complete thorium – uranium fuel cycle with liquid molten salt fuel is still a big technological challenge of the MSR system. However the concurrent fresh fuel processing and the on-line pyrochemical reprocessing technology are necessary to keep the reactor in the long run. The paper describes the existing and present activities in the theoretical and experimental development of suitable fresh thorium fuel processing and on-line separation reprocessing techniques applicable for MSR system working within the thorium – uranium fuel cycle. Special attention is paid to the electrochemical separation processes of uranium, thorium and fission products in molten fluoride salt media, comparison of selected carriers molten salts used during the proposed reprocessing technology and selection of structural materials suitable for molten fluoride salt applications. Further attention is paid to the link between the on-line reprocessing chemistry and the reactor physics which exhibit a mutual retroactive effect. Proceedings of ICAPP 2015.

Czech name

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Czech description

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Type

O - Miscellaneous

CEP classification

DL - Nuclear waste, radioactive pollution and control

OECD FORD branch

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Project

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Continuities

N - Vyzkumna aktivita podporovana z neverejnych zdroju

Publication year

2015

Confidentiality

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