Chemical isolation of .sup.82 Sr from proton-irradiated Mo targets

Title: Chemical isolation of .sup.82 Sr from proton-irradiated Mo targets

Full Record
Other Related Research

Abstract

Spallation reactions are induced in Mo targets with 200-800 MeV protons to produce microcurie to millicurie amounts of a variety of radionuclides. A six-step radiochemical procedure, incorporating precipitation, solvent extractions, and ion exchange techniques, has been developed for the separation and purification of Sr radioactivities from other spallation products and the bulk target material. Radiostrontium can be quantitatively recovered in a sufficiently decontaminated state for use in biomedical generator development.

Inventors:

Grant, Patrick M ^[1]; Kahn, Milton ^[2]; O'Brien, Jr., Harold A. ^[3]

Los Alamos, NM
Albuquerque, NM
(Los Alamos, NM)

Issue Date:: 1976-01-01

Research Org.:: Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

OSTI Identifier:: 862546

Patent Number(s):: 3957945

Assignee:: United States of America as represented by United States Energy (Washington, DC)

Patent Classifications (CPCs):: G - PHYSICS G21 - NUCLEAR PHYSICS G21G - CONVERSION OF CHEMICAL ELEMENTS

Show more

G - PHYSICS G21 - NUCLEAR PHYSICS G21G - CONVERSION OF CHEMICAL ELEMENTS
G21G1/10 - by bombardment with electrically charged particles

Show less

DOE Contract Number:: W-7405-ENG-36

Resource Type:: Patent

Country of Publication:: United States

Language:: English

Subject:: chemical; isolation; 82; sr; proton-irradiated; targets; spallation; reactions; induced; 200-800; mev; protons; produce; microcurie; millicurie; amounts; variety; radionuclides; six-step; radiochemical; procedure; incorporating; precipitation; solvent; extractions; exchange; techniques; developed; separation; purification; radioactivities; products; bulk; target; material; radiostrontium; quantitatively; recovered; sufficiently; decontaminated; biomedical; generator; solvent extraction; target material; spallation products; mev proton; chemical procedure; target mater; solvent extract; /423/376/976/

Citation Formats


                    Grant, Patrick M, Kahn, Milton, and O'Brien, Jr., Harold A. Chemical isolation of .sup.82 Sr from proton-irradiated Mo targets.  United States: N. p., 1976. 
        Web.

Copy to clipboard


                    Grant, Patrick M, Kahn, Milton, & O'Brien, Jr., Harold A. Chemical isolation of .sup.82 Sr from proton-irradiated Mo targets.  United States.

Copy to clipboard


                    Grant, Patrick M, Kahn, Milton, and O'Brien, Jr., Harold A. Thu .  
        "Chemical isolation of .sup.82 Sr from proton-irradiated Mo targets".  United States.  https://www.osti.gov/servlets/purl/862546.

Copy to clipboard


                    
@article{osti_862546,

  title        = {Chemical isolation of .sup.82 Sr from proton-irradiated Mo targets},

  author       = {Grant, Patrick M and Kahn, Milton and O'Brien, Jr., Harold A.},

  abstractNote = {Spallation reactions are induced in Mo targets with 200-800 MeV protons to produce microcurie to millicurie amounts of a variety of radionuclides. A six-step radiochemical procedure, incorporating precipitation, solvent extractions, and ion exchange techniques, has been developed for the separation and purification of Sr radioactivities from other spallation products and the bulk target material. Radiostrontium can be quantitatively recovered in a sufficiently decontaminated state for use in biomedical generator development.},

  doi          = {},

  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {1976},

  month        = {1}

}

Copy to clipboard

Patent:

View Patent

Save / Share:

Export Metadata

Save to My Library

Similar Records in DOE Patents and OSTI.GOV collections:

Hot cell purification of strontium-82, 85 and other isotopes from proton irradiated molybdenum

Patent Bentley, Glenn E [Los Alamos, NM]; Barnes, John W [Los Alamos, NM]

A process suitable for producing curie quantities of quite pure Sr-82,85 is given. After a Mo target is irradiated with energetic protons having energies greater than about 200 MeV, thus producing a large number of radioactive species, the particular species of Sr-82,85 are substantially separated from the other products by a 6-step process. The process comprises dissolution of the target in H.sub.2 O.sub.2, followed by use of several ion exchange resins, extraction with an organophosphorus compound, and several adjustments of pH values. Other embodiments include processes for producing relatively pure long-lived Rb isotopes, Y-88, and Zr-88.
Full Text Available
.sup.82 Sr-.sup.82 Rb Radioisotope generator

Patent Grant, Patrick M [Los Alamos, NM]; Erdal, Bruce R [Los Alamos, NM]; O'Brien, Harold A [Los Alamos, NM]

An improved .sup.82 Sr-.sup.82 Rb radioisotope generator system, based upon the complexing ion exchange resin Chelex-100, has been developed. Columns of this material can be easily and rapidly milked, and the Rb-Sr separation factor for a fresh generator was found to be > 10.sup.7. Approximately 80 percent of the .sup.82 Rb present was delivered in a 15-ml volume of aqueous 0.2 M NH.sub.4 Cl solution. After more than 6 liters of eluant had been put through the generator, the Rb-Sr separation factor was still observed to be > 10.sup.5, and no unusual strontium breakthrough behavior was seen in the systemmore »« less
Full Text Available
Separation of protactinum, actinium, and other radionuclides from proton irradiated thorium target

Patent Fassbender, Michael E.; Radchenko, Valery

Protactinium, actinium, radium, radiolanthanides and other radionuclide fission products were separated and recovered from a proton-irradiated thorium target. The target was dissolved in concentrated HCl, which formed anionic complexes of protactinium but not with thorium, actinium, radium, or radiolanthanides. Protactinium was separated from soluble thorium by loading a concentrated HCl solution of the target onto a column of strongly basic anion exchanger resin and eluting with concentrated HCl. Actinium, radium and radiolanthanides elute with thorium. The protactinium that is retained on the column, along with other radionuclides, is eluted may subsequently treated to remove radionuclide impurities to afford a fractionmore »« less
Full Text Available
Methods for chemical recovery of non-carrier-added radioactive tin from irradiated intermetallic Ti-Sb targets

Patent Lapshina, Elena V [Troitsk, RU]; Zhuikov, Boris L [Troitsk, RU]; Srivastava, Suresh C [Setauket, NY]; ...

The invention provides a method of chemical recovery of no-carrier-added radioactive tin (NCA radiotin) from intermetallide TiSb irradiated with accelerated charged particles. An irradiated sample of TiSb can be dissolved in acidic solutions. Antimony can be removed from the solution by extraction with dibutyl ether. Titanium in the form of peroxide can be separated from tin using chromatography on strong anion-exchange resin. In another embodiment NCA radiotin can be separated from iodide solution containing titanium by extraction with benzene, toluene or chloroform. NCA radiotin can be finally purified from the remaining antimony and other impurities using chromatography on silica gel.more »« less
Full Text Available
Method for fabricating .sup.99 Mo production targets using low enriched uranium, .sup.99 Mo production targets comprising low enriched uranium

Patent Wiencek, Thomas C [Orland Park, IL]; Matos, James E [Oak Park, IL]; Hofman, Gerard L [Downers Grove, IL]

A radioisotope production target and a method for fabricating a radioisotope production target is provided, wherein the target comprises an inner cylinder, a foil of fissionable material circumferentially contacting the outer surface of the inner cylinder, and an outer hollow cylinder adapted to receive the substantially foil-covered inner cylinder and compress tightly against the foil to provide good mechanical contact therewith. The method for fabricating a primary target for the production of fission products comprises preparing a first substrate to receive a foil of fissionable material so as to allow for later removal of the foil from the first substrate,more »« less
Full Text Available

Similar Records