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Title: Pyroprocess for processing spent nuclear fuel

Abstract

This is a pyroprocess for processing spent nuclear fuel. The spent nuclear fuel is chopped into pieces and placed in a basket which is lowered in to a liquid salt solution. The salt is rich in ZrF.sub.4 and containing alkali or alkaline earth fluorides, and in particular, the salt chosen was LiF-50 mol % ZrF.sub.4 with a eutectic melting point of 500.degree. C. Prior to lowering the basket, the salt is heated to a temperature of between 550.degree. C. and 700.degree. C. in order to obtain a molten solution. After dissolution the oxides of U, Th, rare earth and other like oxides, the salt bath solution is subject to hydro-fluorination to remove the oxygen and then to a fluorination step to remove U as gaseous UF.sub.6. In addition, after dissolution, the basket contains PuO.sub.2 and undissolved parts of the fuel rods, and the basket and its contents are processed to remove the Pu.

Inventors:
 [1];  [2]
  1. (Naperville, IL)
  2. (Lockport, IL)
Issue Date:
Research Org.:
Argonne National Laboratory (ANL), Argonne, IL
OSTI Identifier:
874793
Patent Number(s):
6461576
Assignee:
The United States of America as represented by the United States Department (Washington, DC) ANL
DOE Contract Number:  
W-31109-ENG-38
Resource Type:
Patent
Country of Publication:
United States
Language:
English
Subject:
pyroprocess; processing; spent; nuclear; fuel; chopped; pieces; placed; basket; lowered; liquid; salt; solution; rich; zrfsub4; containing; alkali; alkaline; earth; fluorides; chosen; lif-50; mol; eutectic; melting; 500degree; prior; lowering; heated; temperature; 550degree; 700degree; obtain; molten; dissolution; oxides; rare; bath; subject; hydro-fluorination; remove; oxygen; fluorination; step; gaseous; ufsub6; addition; contains; puosub2; undissolved; rods; contents; processed; nuclear fuel; rare earth; alkaline earth; fuel rod; spent nuclear; salt solution; /423/

Citation Formats

Miller, William E., and Tomczuk, Zygmunt. Pyroprocess for processing spent nuclear fuel. United States: N. p., 2002. Web.
Miller, William E., & Tomczuk, Zygmunt. Pyroprocess for processing spent nuclear fuel. United States.
Miller, William E., and Tomczuk, Zygmunt. Tue . "Pyroprocess for processing spent nuclear fuel". United States. https://www.osti.gov/servlets/purl/874793.
@article{osti_874793,
title = {Pyroprocess for processing spent nuclear fuel},
author = {Miller, William E. and Tomczuk, Zygmunt},
abstractNote = {This is a pyroprocess for processing spent nuclear fuel. The spent nuclear fuel is chopped into pieces and placed in a basket which is lowered in to a liquid salt solution. The salt is rich in ZrF.sub.4 and containing alkali or alkaline earth fluorides, and in particular, the salt chosen was LiF-50 mol % ZrF.sub.4 with a eutectic melting point of 500.degree. C. Prior to lowering the basket, the salt is heated to a temperature of between 550.degree. C. and 700.degree. C. in order to obtain a molten solution. After dissolution the oxides of U, Th, rare earth and other like oxides, the salt bath solution is subject to hydro-fluorination to remove the oxygen and then to a fluorination step to remove U as gaseous UF.sub.6. In addition, after dissolution, the basket contains PuO.sub.2 and undissolved parts of the fuel rods, and the basket and its contents are processed to remove the Pu.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2002},
month = {1}
}

Patent:

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