FIELD: removal of radioactive wastes during spent nuclear fuel regeneration. SUBSTANCE: neutron- irradiated graphite is heated in air current at temperature ranging between 450 and 530 C followed by entrapping and settling down extracted compounds of carbon-14. EFFECT: enhanced speed of process. 1 cl, 1 tbl
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Authors
Dates
2003-09-10—Published
2001-07-23—Filed