Progress in thorium fuel cycle technology devoted to molten salt reactor system - 15316
Creators
- 1. Research Centre Rez, Husinec - Rez 130, CZ-250 68 (Czech Republic)
- 2. UJV Rez, Husinec - Rez 130, CZ-250 68 (Czech Republic)
Description
The Molten Salt Reactor (MSR) is one of the Gen IV reactor system, which can be very effectively operated within 232-233U fuel cycle as thorium breeder with the breeding factor significantly higher than 1. Other uniqueness of this reactor system is based on the fact that the primary circuit of the reactor is directly connected with the on-line reprocessing technology necessary for keeping the reactor in operation for a long run. The paper describes the existing and present activities in the area of research and development of fresh thorium - uranium liquid fuel processing, experimental studies of electrochemical separation applicable for on-line reprocessing. The results obtained from measurements show that: -) in FLIBE melt, there is a good possibility for electrochemical removal of uranium, -) in FLINAK melt, only uranium can be directly separated, and -) in LiF-CaF2 melt, uranium, thorium and most of fission products can be electrochemically separated. The theoretical studies of the mutual link between the MSR reactor physics and online reprocessing technology are also presented. It was shown that the noble gases (Xe) and volatile fission products fluorides (Rh) removal helps to prevent more than 98% of overall parasitic absorption on fission products in the core. It is also evident that the reprocessing technology must focus in the first case on lanthanides removal, predominantly on samarium, promethium and neodymium
Additional details
Publishing Information
- Publisher
- Societe Francaise d'Energie Nucleaire - SFEN
- Imprint Place
- Paris (France)
- Imprint Title
- ICAPP 2015 Proceedings
- Imprint Pagination
- 3390 p.
- Journal Page Range
- p. 2715-2717
Conference
- Title
- Nuclear Innovations for a low-carbon future
- Acronym
- ICAPP 2015
- Dates
- 3-6 May 2015
- Place
- Nice (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 49005078
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CALCIUM FLUORIDES; ELECTROCHEMISTRY; FEASIBILITY STUDIES; FISSION PRODUCTS; FUEL REPROCESSING PLANTS; LITHIUM FLUORIDES; MOLTEN SALT FUELED REACTORS; NEODYMIUM; PROMETHIUM; PYROCHEMICAL REPROCESSING; REMOVAL; SAMARIUM; THORIUM CYCLE; THORIUM FLUORIDES; URANIUM; URANIUM 232; URANIUM 233
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDE NUCLEI; ACTINIDES; ALKALI METAL COMPOUNDS; ALKALINE EARTH METAL COMPOUNDS; ALPHA DECAY RADIOISOTOPES; CALCIUM COMPOUNDS; CALCIUM HALIDES; CHEMISTRY; ELEMENTS; EVEN-EVEN NUCLEI; EVEN-ODD NUCLEI; FLUID FUELED REACTORS; FLUORIDES; FLUORINE COMPOUNDS; FUEL CYCLE; HALIDES; HALOGEN COMPOUNDS; HEAVY ION DECAY RADIOISOTOPES; HEAVY NUCLEI; ISOTOPES; LITHIUM COMPOUNDS; LITHIUM HALIDES; MATERIALS; METALS; MOLTEN SALT REACTORS; NEON 24 DECAY RADIOISOTOPES; NUCLEAR FACILITIES; NUCLEI; RADIOACTIVE MATERIALS; RADIOISOTOPES; RARE EARTHS; REACTORS; REPROCESSING; SEPARATION PROCESSES; SPONTANEOUS FISSION RADIOISOTOPES; THORIUM COMPOUNDS; THORIUM HALIDES; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- refs.; This record replaces 48095473