Published September 11, 1998 | Version v1
Patent

Fission product removing device

Description

The present invention provides a method of removing fission products thereby capable of maintaining the purity of plutonium recovered from spent fuel rods. Namely, a spent fuel reprocessing method comprises dissolving spent fuels in molten salts, electrolyzing the same to recover uranium or plutonium. In this process, the removing of fission products is conducted by adding a phosphoric acid compound to the molten salts to convert the fission products into solids, and then separating them to reduce the concentration of the fission products. In this case, a portion of the molten salts is drawn out, fission products are removed from the drawn molten salts. Then, they are returned to the previous molten salts. Control for the amount of the drawn salts enables removal of required amount of fission products. In addition, precipitation and formation of fission products can be prevented upon next dissolution of fuels. (I.S.)

Availability note (English)

Available from JAPIO. Also available from EPO.

Additional details

Publishing Information

Imprint Pagination
8 p.
IPC:
Int. Cl. G21C19/44
IPC
Int. Cl. G21C19/44
Patent number
JP patent document 10-239486/A/

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
30004692
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
DENSITY; FISSION PRODUCTS; FUEL REPROCESSING PLANTS; PLUTONIUM; RADIOACTIVE WASTES; REPROCESSING; SPENT FUELS; URANIUM
Descriptors DEC
ACTINIDES; ELEMENTS; ENERGY SOURCES; FUELS; ISOTOPES; MATERIALS; METALS; NUCLEAR FACILITIES; NUCLEAR FUELS; PHYSICAL PROPERTIES; RADIOACTIVE MATERIALS; REACTOR MATERIALS; SEPARATION PROCESSES; TRANSURANIUM ELEMENTS; WASTES

Optional Information

Secondary number(s)
JP patent application 9-38798