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Title: PROCESSES AND TECHNIQUE FOR THE RECOVERY OF NEPTUNIUM-237 FROM A PUREX-TYPE SOLVENT EXTRACTION PLANT PROCESSING IRRADIATED URANIUM FUEL ELEMENTS

Abstract

A technique is outlined for removing accumulated Np/sup 237/ from the aqueous raffinate in the Purex Process. The technique comprises processing the solutions prior to plant shutdown to accumulate essentially all of the Np/sup 237/ in the waste backcycle, adjusting the chemical composition of this feed material, and processing the feed to achieve purification, decontamination, and concentration of the Np/sup 237/ into a small volume of nitrate solution. Chemical flowsheets are given. (D.L.C.)

Authors:
;
Publication Date:
Research Org.:
General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
OSTI Identifier:
4087340
Report Number(s):
HW-56675(Del.)
NSA Number:
NSA-18-013910
DOE Contract Number:  
AT(45-1)-1350
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-64
Country of Publication:
United States
Language:
English
Subject:
CHEMISTRY; DECONTAMINATION; DIAGRAMS; ENRICHMENT; FISSION PRODUCTS; FLUID FLOW; FUEL ELEMENTS; IRRADIATION; NEPTUNIUM 237; NEPTUNIUM COMPOUNDS; NEPTUNIUM NITRATES; NITRATES; OPERATION; PLANNING; PUREX PROCESS; QUALITATIVE ANALYSIS; RADIOCHEMISTRY; RECOVERY; REFINING; REPROCESSING; SHUTDOWN; SOLUTIONS; SOLVENT EXTRACTION; URANIUM; VOLUME; WASTE PROCESSING; WASTE SOLUTIONS; WATER

Citation Formats

Swift, W H, and Beard, S J. PROCESSES AND TECHNIQUE FOR THE RECOVERY OF NEPTUNIUM-237 FROM A PUREX-TYPE SOLVENT EXTRACTION PLANT PROCESSING IRRADIATED URANIUM FUEL ELEMENTS. United States: N. p., 1958. Web.
Swift, W H, & Beard, S J. PROCESSES AND TECHNIQUE FOR THE RECOVERY OF NEPTUNIUM-237 FROM A PUREX-TYPE SOLVENT EXTRACTION PLANT PROCESSING IRRADIATED URANIUM FUEL ELEMENTS. United States.
Swift, W H, and Beard, S J. Tue . "PROCESSES AND TECHNIQUE FOR THE RECOVERY OF NEPTUNIUM-237 FROM A PUREX-TYPE SOLVENT EXTRACTION PLANT PROCESSING IRRADIATED URANIUM FUEL ELEMENTS". United States.
@article{osti_4087340,
title = {PROCESSES AND TECHNIQUE FOR THE RECOVERY OF NEPTUNIUM-237 FROM A PUREX-TYPE SOLVENT EXTRACTION PLANT PROCESSING IRRADIATED URANIUM FUEL ELEMENTS},
author = {Swift, W H and Beard, S J},
abstractNote = {A technique is outlined for removing accumulated Np/sup 237/ from the aqueous raffinate in the Purex Process. The technique comprises processing the solutions prior to plant shutdown to accumulate essentially all of the Np/sup 237/ in the waste backcycle, adjusting the chemical composition of this feed material, and processing the feed to achieve purification, decontamination, and concentration of the Np/sup 237/ into a small volume of nitrate solution. Chemical flowsheets are given. (D.L.C.)},
doi = {},
url = {https://www.osti.gov/biblio/4087340}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1958},
month = {7}
}

Technical Report:
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