Pyrochemical reprocessing method for spent nuclear fuel
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United States of America Patent
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Jan 29, 2008
Grant Date -
Jul 19, 2007
app pub date -
Jun 1, 2004
filing date -
May 25, 2001
priority date (Note) -
Expired
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Abstract
This invention is provided for improvement of corrosion-resistant property of a crucible and for promotion of safety in a pyrochemical reprocessing method for the spent nuclear fuel. The spent nuclear fuel is dissolved in a molten salt placed in the crucible. In a pyrochemical reprocessing method, the nuclear fuel is deposited, and the crucible (2) is heated by induction heating. Cooling media (5, 6) are supplied to cool down, and a molten salt layer (7) is maintained by keeping balance between the heating and the cooling, and a solidified salt layer (8) is formed on inner wall surface of the crucible.
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