System analysis of molten salt reactor fuel reprocessing

Result code in IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F46356088%3A_____%2F11%3A%230001095" target="_blank" >RIV/46356088:_____/11:#0001095 - 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

System analysis of molten salt reactor fuel reprocessing

Original language description

The main advantage of the thorium - uranium fuel cycle is in the minimized production of long-lived radioactive waste, which moreover does not contain any transplutonium elements. However the transition to the thorium - uranium fuel cycle can be attractive only if a reactor system will be able to produce new fissile material (233U) fast enough. The double-fluid MSR system can fulfill these demands well, and its design simplifies significantly the demandingness of the on-line reprocessing technology.

Czech name

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Czech description

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Type

J_x - Unclassified - Peer-reviewed scientific article (Jimp, Jsc and Jost)

CEP classification

JF - Nuclear energy

OECD FORD branch

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Project

<a href="/en/project/2A-1TP1%2F030" target="_blank" >2A-1TP1/030: Fluoride reprocessing of spent fuel of Beneration IV reactors</a><br>

Continuities

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Publication year

2011

Confidentiality

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

Name of the periodical

Transactions of the American Nuclear Society

ISSN

0003-018X

e-ISSN

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Volume of the periodical

104

Issue of the periodical within the volume

1

Country of publishing house

US - UNITED STATES

Number of pages

2

Pages from-to

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UT code for WoS article

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EID of the result in the Scopus database

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