Process for separating fission product molybdenum from an irradi

Details Process for separating fission product molybdenum from an irradi Process for separating fission product molybdenum from an irradi

1977-02-17

1978-10-31

Miller, Edward A.

Chemistry of inorganic compounds

Treating mixture to obtain metal containing compound

Radioactive metal

423 59, C01G 3900

Patent

active

041234987

ABSTRACT:
A process for the separation and collection of molybdenum-99 from an irradiated uranium-containing target material utilizes thermal chromatographic separation. The irradiated target material containing the molybdenum-99 is heated in an oxidizing atmosphere to form an oxidized target material and gaseous molybdenum-99 trioxide. The gaseous molybdenum-99 trioxide is carried by the oxidizing atmosphere along with other vaporized materials to a cooling zone for progressive condensation and collection of the molybdenum-99 trioxide and the other materials in the form of separate deposits.

REFERENCES:
patent: 1629004 (1927-05-01), Schwarzkopf
patent: 1815132 (1931-07-01), Schwarzkopf
patent: 3833469 (1974-09-01), Robson
patent: 3848050 (1974-11-01), Jemal
patent: 4017583 (1977-04-01), Motojima et al.
Motojima II, International Journal of Applied Radiation and Isotopes, 27, 495-498, Pergamon Press (1976), Northern Ireland.
Castleman et al., Nuclear Science and Engineering, 29, 159-164, (1967).

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