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Synthesis and characterization of uranium trichloride in alkali-metal chloride media

Journal Article · · Journal of Nuclear Materials
 [1];  [2];  [3];  [3];  [3];  [3]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States); Univ. of Idaho, Idaho Falls, ID (United States)
  2. Univ. of Idaho, Idaho Falls, ID (United States)
  3. Idaho National Lab. (INL), Idaho Falls, ID (United States)
+ Show Author Affiliations

Given a growing interest in uranium salts for pyrochemical processing of used fuel and uranium-fueled molten salt reactors, the synthesis of uranium trichloride in alkali-metal chloride media was investigated in a series of four experiments. Specifically, uranium metal powder and uranium hydride powder were prepared and separately blended with ammonium chloride and lithium chloride – potassium chloride eutectic in two runs, while the same powders were separately blended with ammonium chloride and sodium chloride in two additional runs. Each of the lithium chloride – potassium chloride containing blends was slowly heated to 923 K, while those containing sodium chloride were heated to 1123 K. During each heat up, the ammonium chloride sublimed into gaseous ammonia and hydrogen chloride, leading to the chlorination of uranium metal or uranium hydride and the formation of molten salt solutions of the respective chlorides. Experimental conditions were incorporated in the runs to promote formation of uranium trichloride over uranium tetrachloride in the respective media. Molten samples of each run product were taken and characterized via chemical analyses, diffractometry, and microscopy. The final products from each run were dark dense ingots of the respective salt systems with uranium concentrations ranging from 44 to 51 wt%. Finally, chemical analyses and diffractometry identified the predominant presence of uranium trichloride in these systems; however, a possible minor presence of uranium tetrachloride could not be conclusively dismissed.

Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE); USDOE Laboratory Directed Research and Development (LDRD) Program
Grant/Contract Number:
AC07-05ID14517
OSTI ID:
1958723
Alternate ID(s):
OSTI ID: 1960632
Report Number(s):
INL/JOU-21-61924-Rev000
Journal Information:
Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 565; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (6)

A study on chlorination of uranium metal using ammonium chloride journal July 2017
Preparation of uranium(III) in a molten chloride salt: a redox mechanistic study journal June 2018
Synthesis of uranium trichloride salt using ZnCl2 journal August 2018
Experimental investigations and thermodynamic modelling of KCl–LiCl–UCl3 system journal June 2014
Recycling of Uranium from Uranium-Aluminium alloys by Chlorination with HCl(g) journal January 2012
Phase Equilibria Studies of the LiCl-KCl-UCl 3 System journal April 2018

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Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
Ammonium chloride
Uranium hydride chlorination
Uranium metal chlorination
Uranium trichloride characterization
Uranium trichloride synthesis