ARSENATE CARRIER PRECIPITATION METHOD OF SEPARATING PLUTONIUM FROM NEUTRON IRRADIATED URANIUM AND RADIOACTIVE FISSION PRODUCTS

Title: ARSENATE CARRIER PRECIPITATION METHOD OF SEPARATING PLUTONIUM FROM NEUTRON IRRADIATED URANIUM AND RADIOACTIVE FISSION PRODUCTS

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Abstract

A process is described for precipitating Pu from an aqueous solution as the arsenate, either per se or on a bismuth arsenate carrier, whereby a separation from uranium and fission products, if present in solution, is accomplished.

Inventors:: Thompson, S.G.; Miller, D.R.; James, R.A.

Issue Date:: 1961-06-20

Research Org.:: Originating Research Org. not identified

OSTI Identifier:: 4005026

Patent Number(s):: 2989367

Assignee:: U.S. Atomic Energy Commission DTIE; NSA-15-019473

NSA Number:: NSA-15-019473

Resource Type:: Patent

Resource Relation:: Other Information: Orig. Receipt Date: 31-DEC-61

Country of Publication:: United States

Language:: English

Subject:: CHEMISTRY; ARSENIC COMPOUNDS; BISMUTH; FISSION PRODUCTS; IRRADIATION; NEUTRONS; PLUTONIUM; PRECIPITATION; SEPARATION PROCESSES; SOLUTIONS; URANIUM; WATER

Citation Formats


                    Thompson, S.G., Miller, D.R., and James, R.A. ARSENATE CARRIER PRECIPITATION METHOD OF SEPARATING PLUTONIUM FROM NEUTRON IRRADIATED URANIUM AND RADIOACTIVE FISSION PRODUCTS.  United States: N. p., 1961. 
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                    Thompson, S.G., Miller, D.R., & James, R.A. ARSENATE CARRIER PRECIPITATION METHOD OF SEPARATING PLUTONIUM FROM NEUTRON IRRADIATED URANIUM AND RADIOACTIVE FISSION PRODUCTS.  United States.

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                    Thompson, S.G., Miller, D.R., and James, R.A. Tue .  
        "ARSENATE CARRIER PRECIPITATION METHOD OF SEPARATING PLUTONIUM FROM NEUTRON IRRADIATED URANIUM AND RADIOACTIVE FISSION PRODUCTS".  United States.

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@article{osti_4005026,

  title        = {ARSENATE CARRIER PRECIPITATION METHOD OF SEPARATING PLUTONIUM FROM NEUTRON IRRADIATED URANIUM AND RADIOACTIVE FISSION PRODUCTS},

  author       = {Thompson, S.G. and Miller, D.R. and James, R.A.},

  abstractNote = {A process is described for precipitating Pu from an aqueous solution as the arsenate, either per se or on a bismuth arsenate carrier, whereby a separation from uranium and fission products, if present in solution, is accomplished.},

  doi          = {},

  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {1961},

  month        = {6}

}

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