On the Posibility of Quantitative Electrochemical Separation of Uranium from Gadolinium in Fluoride Melts
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F18%3AN0000087" target="_blank" >RIV/26722445:_____/18:N0000087 - isvavai.cz</a>
Result on the web
<a href="https://ans.org/pubs/transactions/a_43585" target="_blank" >https://ans.org/pubs/transactions/a_43585</a>
DOI - Digital Object Identifier
—
Alternative languages
Result language
angličtina
Original language name
On the Posibility of Quantitative Electrochemical Separation of Uranium from Gadolinium in Fluoride Melts
Original language description
The Molten Salt Reactor (MSR) is a non-classical (liquid fuel) system which can be operated as a breeder within the 232Th-233U fuel cycle with the very interesting breeding factor. The necessary precondition for its proper functionality is the on-line reprocessing within the MSR´s fuel cycle. Therefore, a lot of effort is given to the development of the on-line pyrochemical reprocessing technology. Among the processes considered to be suitable for this process, the electrochemical separations are highlighted. Within this context, it is necessary to study electrochemical behavior of both fissile material and fission products in the molten salt systems and to develop the processes of their extraction from the system at various stages of the whole cycle. More details about MSR on-line reprocessing technology and also its connection to nonproliferation aspects can be found here.1 In this contribution, continuation of the study of the electrochemical separation of U from Gd in the LiF-CaF2 molten system by the modulated current electrolysis is presented.
Czech name
—
Czech description
—
Classification
Type
D - Article in proceedings
CEP classification
—
OECD FORD branch
20305 - Nuclear related engineering; (nuclear physics to be 1.3);
Result continuities
Project
<a href="/en/project/TH02020113" target="_blank" >TH02020113: Research and development of fluoride salt-cooled nuclear reactor systems</a><br>
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Others
Publication year
2018
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Article name in the collection
Transactions of the American Nuclear Society
ISBN
—
ISSN
0003-018X
e-ISSN
—
Number of pages
2
Pages from-to
118-119
Publisher name
American Nuclear Society
Place of publication
—
Event location
Philladelphia, USA
Event date
Jun 17, 2018
Type of event by nationality
WRD - Celosvětová akce
UT code for WoS article
—