SODIUM FLUORIDE AS A SPECTROSCOPIC CARRIER FOR PLUTONIUM METAL ANALYSIS
Abstract
A pyroelectric carrier distillation method, using sodium fluoride as a spectroscopic carrier, was developed for the impurity analysis of plutonium metal. (auth)
- Authors:
- Publication Date:
- Research Org.:
- Dow Chemical Co. Rocky Flats Plant, Denver
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 4216351
- Report Number(s):
- RFP-143
- NSA Number:
- NSA-13-021963
- DOE Contract Number:
- AT(29-1)-1106
- Resource Type:
- Technical Report
- Resource Relation:
- Other Information: Decl. July 30, 1959. Orig. Receipt Date: 31-DEC-59
- Country of Publication:
- United States
- Language:
- English
- Subject:
- CHEMISTRY; CARRIERS; DISTILLATION; ELECTRIC ARCS; EMISSION; IMPURITIES; LIGHT; METALS; PLUTONIUM; QUALITATIVE ANALYSIS; SODIUM FLUORIDES; SPECTROSCOPY
Citation Formats
Johnson, A.J., and Vejvoda, E. SODIUM FLUORIDE AS A SPECTROSCOPIC CARRIER FOR PLUTONIUM METAL ANALYSIS. United States: N. p., 1959.
Web. doi:10.2172/4216351.
Johnson, A.J., & Vejvoda, E. SODIUM FLUORIDE AS A SPECTROSCOPIC CARRIER FOR PLUTONIUM METAL ANALYSIS. United States. doi:10.2172/4216351.
Johnson, A.J., and Vejvoda, E. Mon .
"SODIUM FLUORIDE AS A SPECTROSCOPIC CARRIER FOR PLUTONIUM METAL ANALYSIS". United States.
doi:10.2172/4216351. https://www.osti.gov/servlets/purl/4216351.
@article{osti_4216351,
title = {SODIUM FLUORIDE AS A SPECTROSCOPIC CARRIER FOR PLUTONIUM METAL ANALYSIS},
author = {Johnson, A.J. and Vejvoda, E.},
abstractNote = {A pyroelectric carrier distillation method, using sodium fluoride as a spectroscopic carrier, was developed for the impurity analysis of plutonium metal. (auth)},
doi = {10.2172/4216351},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Apr 20 00:00:00 EST 1959},
month = {Mon Apr 20 00:00:00 EST 1959}
}
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Evaluation of the equivalent dose rates due to neutrons emitted by plutonium metal, plutonium oxide, and plutonium fluoride: graphs; Evaluation des debits d'equivalent de dose dus aux neutrons issus du plutonium metal, de l'oxyde de plutonium, du fluorure de plutonium. Abaques (in French)
In irradiated fuel processing plants, the personnel concerned with radloprotection often require a rapid estimation of the equivalent dose rates due to neutrons emitted by plutonium or plutonium compound sources (sources having different physical and geometrical characteristics). GraphPS are presented which facilitate rapid determinations. Expressions enabling the specific emissions of Pu or Pu compound sources to be calculated are given, the contribution of the flssion neutrons produced being taken into consideration. This Pu can arise from fuels having different physical characteristics. As an example of the application of the techniques outlined, graphs enabling the equivalent dose rates to be evaluatedmore » -
THE LANTHANUM FLUORIDE CO-PRECIPITATION METHOD FOR THE DETERMINATION OF PLUTONIUM THE EFFICIENCY OF PRECIPITATION OF THE LANTHANUM CARRIER AS FLUORIDE
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Recovery of plutonium from sodium fluoride and alumina traps loaded with plutonium tetrafluoride
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Preparation of Plutonium Fluoride to Obtain Metal of High Purity; PREPARATION DE FLUORURES DE PLUTONIUM POUR L'OBTENTION DE METAL DE HAUTE PURETE
In the process of treating irradiated uranium, plutonium can be separated from the majority of the fission products and from the uranium by TBP extraction cycles. The high purity necessary for metallurgical and nuclear physics experiments led us to consider more elaborate purification processes, and a specially adapted method of fluoride preparation. Purification cycles of plutonium in solution on ion exchange resins are described, and the results are given. The description and results of the fluoride preparation method are also given. (auth)