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Title: Pyrochemical recovery of actinide elements from spent light water reactor fuel

Abstract

Argonne National Laboratory is investigating salt transport and lithium pyrochemical processes for recovery of transuranic (TRU) elements from spent light water reactor fuel. The two processes are designed to recover the TRU elements in a form compatible with the Integral Fast Reactor (IFR) fuel cycle. The IFR is uniquely effective in consuming these long-lived TRU elements. The salt transport process uses calcium dissolved in Cu-35 wt % Mg in the presence of a CaCl{sub 2} salt to reduce the oxide fuel. The reduced TRU elements are separated from uranium and most of the fission products by using a MgCl{sub 2} transport salt. The lithium process, which does not employ a solvent metal, uses lithium in the presence of a LiCl salt as the reductant. After separation from the salt, the reduced metal is introduced into an electrorefiner, which separates the TRU elements from the uranium and fission products. In both processes, reductant and reduction salt are recovered by electrochemical decomposition of the oxide reaction product.

Authors:
; ; ;
Publication Date:
Research Org.:
Argonne National Lab., IL (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
10115894
Report Number(s):
ANL/CMT/CP-80020; CONF-940204-4
ON: DE94005386; TRN: 94:002268
DOE Contract Number:  
W-31109-ENG-38
Resource Type:
Conference
Resource Relation:
Conference: 123. annual meeting of the Minerals, Metals and Materials Society,San Francisco, CA (United States),27 Feb - 3 Mar 1994; Other Information: PBD: [1994]
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; SPENT FUELS; PYROCHEMICAL REPROCESSING; ACTINIDES; MATERIALS RECOVERY; TRANSURANIUM ELEMENTS; SEPARATION PROCESSES; ELECTROREFINING; CHEMICAL REACTIONS; MAGNESIUM CHLORIDES; LITHIUM CHLORIDES; 050800; SPENT FUELS REPROCESSING

Citation Formats

Johnson, G K, Pierce, R D, Poa, D S, and McPheeters, C C. Pyrochemical recovery of actinide elements from spent light water reactor fuel. United States: N. p., 1994. Web.
Johnson, G K, Pierce, R D, Poa, D S, & McPheeters, C C. Pyrochemical recovery of actinide elements from spent light water reactor fuel. United States.
Johnson, G K, Pierce, R D, Poa, D S, and McPheeters, C C. Sat . "Pyrochemical recovery of actinide elements from spent light water reactor fuel". United States. https://www.osti.gov/servlets/purl/10115894.
@article{osti_10115894,
title = {Pyrochemical recovery of actinide elements from spent light water reactor fuel},
author = {Johnson, G K and Pierce, R D and Poa, D S and McPheeters, C C},
abstractNote = {Argonne National Laboratory is investigating salt transport and lithium pyrochemical processes for recovery of transuranic (TRU) elements from spent light water reactor fuel. The two processes are designed to recover the TRU elements in a form compatible with the Integral Fast Reactor (IFR) fuel cycle. The IFR is uniquely effective in consuming these long-lived TRU elements. The salt transport process uses calcium dissolved in Cu-35 wt % Mg in the presence of a CaCl{sub 2} salt to reduce the oxide fuel. The reduced TRU elements are separated from uranium and most of the fission products by using a MgCl{sub 2} transport salt. The lithium process, which does not employ a solvent metal, uses lithium in the presence of a LiCl salt as the reductant. After separation from the salt, the reduced metal is introduced into an electrorefiner, which separates the TRU elements from the uranium and fission products. In both processes, reductant and reduction salt are recovered by electrochemical decomposition of the oxide reaction product.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1994},
month = {1}
}

Conference:
Other availability
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