U.S. patents available from 1976 to present.
U.S. patent applications available from 2005 to present.

Process for the recovery of molybdenum-99 from an irradiated uranium alloy target

Patent 4701308 Issued on October 20, 1987. Estimated Expiration Date: Icon_subject December 10, 2005. Estimated Expiration Date is calculated based on simple USPTO term provisions. It does not account for terminal disclaimers, term adjustments, failure to pay maintenance fees, or other factors which might affect the term of a patent.

Patent References

3382152

3799883

3821351

3900551

Molybdenum recovery
Patent #: 3933971
Issued on: 01/20/1976
Inventor: Baucom

Preparation of a primary target for the production of fission products in a nuclear reactor
Patent #: 3940318
Issued on: 02/24/1976
Inventor: Arino ,   et al.

Process for recovering molybdenum-99 from a matrix containing neutron irradiated fissionable materials and fission products
Patent #: 4093697
Issued on: 06/06/1978
Inventor: Hadi, et al.

Process for recovering molybdenum-99 from a matrix containing neutron irradiated fissionable materials and fission products
Patent #: 4094953
Issued on: 06/13/1978
Inventor: Hadi, et al.

Method for enhanced control of radioiodine in the production of fission product molybdenum 99
Patent #: 4284472
Issued on: 08/18/1981
Inventor: Pomares ,   et al.

Separation of uranium and molybdenum using a solvent Patent #: 4363788
Issued on: 12/14/1982
Inventor: Floreancig ,   et al.

Inventors

Assignee

Application

No. 06/806815 filed on 12/10/1985

US Classes:

423/2, Radioactive metal (At. No. 84+ or radioactive isotope of another metal)252/645, For tracing, tagging, or testing423/9Organo-nitrogen solvent

Examiners

Primary: Miller, Edward A.

Attorney, Agent or Firm

International Classes

C01G 39/00 (20060101)
C22B 3/00 (20060101)
C22B 3/32 (20060101)
G21G 1/08 (20060101)
G21C 19/42 (20060101)
G21C 19/46 (20060101)
G21G 1/00 (20060101)

Foreign Application Priority Data

1984-12-28 FR

Abstract

The invention relates to a process for the recovery of molybdenum-99 from an irradiated uranium alloy target.This process comprises the following stages:(a) dissolving the irradiated uranium alloy target in sulphuric acid,(b) separating the iodine and tellurium present in the thus obtained solution,(c) oxidizing the molybdenum-99 present in the Mo (VI) solution, and(d) extracting the thus oxidized molybdenum-99 with a hydroxamic acid of formula: ##STR1## in which R is a radical chosen from the group including straight or branched-chain alkyl radicals, the phenyl radical, phenyl radicals substituted by at least one alkyl radical, arylalkyl radicals and the cyclohexyl radical and R' is a hydrogen atom or an alkyl radical.The hydroxamic acid can be tri-n-butylacetohydroxamic acid and the molybdenum recovered can be used in a technetium generator for medical purposes.

Other References

  • Chemical Abstracts, vol. 83, 1975, p. 706, No. 157388u, Gupta et al.: "Hydroxamic Acids. XIV. Reactions of N-arylhydroxamic Acids with Metal Ions"
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