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Title: Compression of lithium fluoride to 92GPa

Authors:
; ; ; ; ; ;  [1];  [2];  [2];  [2]
  1. Princeton
  2. (
Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States). Advanced Photon Source (APS)
Sponsoring Org.:
NSFDOE - BASIC ENERGY SCIENCES
OSTI Identifier:
1123929
Resource Type:
Journal Article
Resource Relation:
Journal Name: High Pressure Research; Journal Volume: 34; Journal Issue: 1
Country of Publication:
United States
Language:
ENGLISH

Citation Formats

Dong, Haini, Dorfman, Susannah M., Holl, Christopher M., Meng, Yue, Prakapenka, Vitali B., He, Duanwei, Duffy, Thomas S., CIW), UC), and Sichuan U.). Compression of lithium fluoride to 92GPa. United States: N. p., 2016. Web. doi:10.1080/08957959.2013.878932.
Dong, Haini, Dorfman, Susannah M., Holl, Christopher M., Meng, Yue, Prakapenka, Vitali B., He, Duanwei, Duffy, Thomas S., CIW), UC), & Sichuan U.). Compression of lithium fluoride to 92GPa. United States. doi:10.1080/08957959.2013.878932.
Dong, Haini, Dorfman, Susannah M., Holl, Christopher M., Meng, Yue, Prakapenka, Vitali B., He, Duanwei, Duffy, Thomas S., CIW), UC), and Sichuan U.). 2016. "Compression of lithium fluoride to 92GPa". United States. doi:10.1080/08957959.2013.878932.
@article{osti_1123929,
title = {Compression of lithium fluoride to 92GPa},
author = {Dong, Haini and Dorfman, Susannah M. and Holl, Christopher M. and Meng, Yue and Prakapenka, Vitali B. and He, Duanwei and Duffy, Thomas S. and CIW) and UC) and Sichuan U.)},
abstractNote = {},
doi = {10.1080/08957959.2013.878932},
journal = {High Pressure Research},
number = 1,
volume = 34,
place = {United States},
year = 2016,
month = 7
}
  • Spectra are presented for nickel fluoride, cobalt fluoride, chromic fluoride, praseodymium fluoride, uranium tetrafluoride, and uranyl fluoride dissolved in molten lithium fluoride-sodium fluoride-potassium fluoride at temperatures ranging from 500° to approximately 650°C. These spectra are compared to similar spectra obtained in other molten salts and aqueous solutions. General procedures are described which were used in preparing the fluoride salt melt and in recording the spactra by means of a high-temperature cell assembly designed for use with a Cary recording spectrophotometer, Model 14M.
  • Spectra are presented for solutions of praseodymium, neodymium, and samarium fluoride in molten lithium fluoride at approximately 900/sup deg /C. These data are discussed and compared to similar results that were obtained in other molten salts and aqueous solutions. Molar absorptivities for selected major absorbance peaks of these rare-earth spectra are given. (auth)
  • The voltammetty of iron(II) in molten LiF-NaF-KF was investigated over the temperature range 470-545 deg C. The current-voltage curves were recorded using a controlled-potential polarograph and a stationary platinum micro- electrode coupled with a platinum quasi-reference electrode. A third platinum electrode, which was isolated, served as the counter electrode. The reduction of iron(II) to the metal and the oxidation of iron(II) to iron(III) appeared to proceed reversibly under the existing experimental conditions. The limiting current (wave height) of the cathodic wave was proportional to the concentration of iron in the melt. An activation energy of about 12 kcal/ mole wasmore » calculated for the current limiting process, which corresponded to the reduction of iron(II) to the metal. (auth)« less
  • Low-pressure distillation of molten-salt nuclear reactor fuels was demonstrated by processing, at 1000 deg C, six 38-l. batches of nonradioactive mixtures of LiF, BeF/sub 2/, ZrF/sub 4/, and NdF/sub 3/, and one 12-l. batch of irradiated fuel carrier salt from the molten salt reactor experiment. A distillation rate of 1.5 ft/sup 3/ of salt per day per square foot of vaporization surface was achieved. Evidences of concentration polarization and/ or entrainndent were noted. Automatic operation was easily maintained in each run. Condensation of volatile salt components in the vacuum lines and metal deposition in the feed line to the stillmore » pot are problems needing further attention. Results of the nonradioactive tests indicate that the application of distillation to molten-salt breeder reactor fuel salt processing is feasible.« less