Published November 1, 1996 | Version v1
Patent

Solidification method for radioactive waste

Description

When the weight of an ordinary portland cement is defined as A, and the weight of an amorphous silica-type addition member is defined as B, those satisfying 0.20 ≤ B/(A+B) ≤ 0.8 are used as a cement-type solidification material. Accordingly, radioactive wastes containing sodium sulfate as a soluble inorganic compound are devolumed by pellet-solidification and calcination-solidification or the like, and 35kg of the radioactive wastes are filled per 200L of the solidification material, the distribution coefficient of C-14 can be kept to higher 500mL/g which is a safety standard value. Accordingly, the radioactive wastes can be discarded while being devolumed compared with a case of not using the amorphous silica-type addition material in which 200L of the solidification material is used for 30kg of radioactive wastes. (T.M.)

Availability note (English)

Available from JAPIO. Also available from EPO.

Additional details

Publishing Information

Imprint Pagination
12 p.
IPC:
Int. Cl. G21F9/30; G21F9/16.
IPC
Int. Cl. G21F9/30; G21F9/16.
Patent number
JP patent document 8-285995/A/

Optional Information

Secondary number(s)
JP patent application 7-93857.