Apparatus for subjecting a radioactive sodium borate waste solut

Details Apparatus for subjecting a radioactive sodium borate waste solut Apparatus for subjecting a radioactive sodium borate waste solut

1986-03-20

1987-12-01

Bashore, S. Leon

Concentrating evaporators

Film type

Moving-film support

159 251, 159DIG12, 422159, 422903, 252629, 219 1055A, B01D 122, G21F 908, G21F 916

Patent

active

047102667

ABSTRACT:
An apparatus is disclosed for producing a vitric solid solution comprising mainly the solid content of a radioactive waste solution of sodium borate discharged from a pressurized water reactor, the apparatus comprising a waste solution feed tank equipped with a hopper for stabilizing agent in water, a thin film evaporator, a heating type dehydrator, a powder drier connected with a microwave generator through a microwave guide tube and equipped with a stirrer, and a melting furnace connected with a microwave generator through a microwave guide tube, the above units being combined by pipes or a powder-transferring means.

REFERENCES:
patent: 4221680 (1980-09-01), Hardwick et al.
patent: 4341915 (1982-07-01), Adachi et al.
patent: 4344872 (1982-08-01), Thiele
patent: 4409137 (1983-10-01), Mergan et al.
patent: 4452733 (1984-06-01), Horiuchi et al.
Odoj, "Glas als Werkstoff zur Beseitigung Radioaktier Abfalle", Sprechsal 113, Jahrgang, Heft 5/80, pp. 345-350.
Heimerl et al., "Chemical and Technological Aspects of the Vitrification of High Level Radioactive Wastes", Kerntechnik 18, Jahrgang (1976), No. 6, pp. 272-277.
Preprint G 46 (Oct. 1978) of 1978 Fall Meeting of Atomic Energy Society of Japan.
Summary Report J 39 (Mar. 1979) of 1979 Annual Meeting (17th) of Atomic Energy Society of Japan.
Preprint F 74 (Oct. 1979) of Fall Meeting of Atomic Energy Society of Japan.
Preprint, p. 58 (Oct. 1980) of 13th Reporting and Lecture Meeting of Power Reactor and Nuclear Fuel Development Corporation.
Preprint G 47 (Oct. 1979) of 1979 Fall Meeting of Atomic Energy Society of Japan.
Summary Report F 31 of 1981 Annual Meeting of Atomic Energy Society of Japan.
Preprint F-9 of the Fall Meeting, 1980 of the Atomic Energy Society of Japan.
Glass Handbook 3.2.4 Borosilicate Glass.
JAERI-M 82-007, "Corrosion Resistance of Metal Materials for HLW Canister", Furuya et al., 2/82.
"The Invention", vol. 80, No. 5, pp. 58-62.
Summary Report F 25 of 1978 Annual Meeting of Atomic Energy Society of Japan (Mar. 1978).
Summary Report J 37 (Mar. 1979) of 1979 Annual Meeting (17th) of Atomic Energy Society of Japan.
Kobe Steel Technical Report, vol. 33, No. 1, pp. 35-38.

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