Fuel salt and container material studies for MOSART transforming system

Conference · Mon Jul 01 00:00:00 EDT 2013

OSTI ID:22264118

Ignatiev, V.; Feynberg, O.; Merzlyakov, A.; Surenkov, A.; Zagnitko, A. ^[1]; Afonichkin, V.; Bovet, A.; Khokhlov, V. ^[2]; Subbotin, V.; Gordeev, M.; Panov, A.; Toropov, A. ^[3]

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1. National Research Center, Kurchatov Institute, Moscow (Russian Federation)
2. Institute of High Temperature Electrochemisty, Ekaterinburg (Russian Federation)
3. Institute of Technical Physics, Snezhinsk (Russian Federation)

A study is under progress to examine the feasibility of single stream Molten Salt Actinide Recycling and Transmuting system without and with Th support (MOSART) fuelled with different compositions of actinide tri-fluorides (AnF{sub 3}) from used LWR fuel. New fast-spectrum design options with homogeneous core and fuel salts with high enough solubility for AnF{sub 3} are being examined because of new goals. The flexibility of single fluid MOSART concept with Th support is underlined, particularly, possibility of its operation in self-sustainable mode (Conversion Ratio: CR=1) using different loadings and make up. The paper summarizes the most current status of fuel salt and container material data for the MOSART concept received within ISTC-3749 and ROSATOM-MARS projects. Key physical and chemical properties of various fluoride fuel salts are reported. The issues like salt purification, the electroreduction of U(IV) to U(III) in LiF-ThF{sub 4} and the electroreduction of Yb(III) to Yb(II) in LiF-NaF are detailed.

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 22264118
• Resource Relation: Conference: GLOBAL 2013: International Nuclear Fuel Cycle Conference - Nuclear Energy at a Crossroads, Salt Lake City, UT (United States), 29 Sep - 3 Oct 2013; Other Information: Country of input: France; 19 refs.; Related Information: In: Proceedings of GLOBAL 2013: International Nuclear Fuel Cycle Conference - Nuclear Energy at a Crossroads| 1633 p.
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
CHEMICAL PROPERTIES
LITHIUM FLUORIDES
LOADING
MODE CONVERSION
MOLTEN SALTS
NUCLEAR FUELS
PURIFICATION
RECYCLING
SODIUM FLUORIDES
SOLUBILITY
THORIUM FLUORIDES