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Title: Feasibility of Direct Disposal of Electrorefiner Salt Waste.

Abstract

Abstract not provided.

Authors:
; ; ; ; ; ; ;
Publication Date:
Research Org.:
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE), Nuclear Facility Operations (NE-3)
OSTI Identifier:
1397120
Report Number(s):
SAND2016-9650C
647789
DOE Contract Number:
AC04-94AL85000
Resource Type:
Conference
Resource Relation:
Conference: Proposed for presentation at the International High Level Radioactive Waste Management Conference held April 9-14, 2017 in Charlotte, NC.
Country of Publication:
United States
Language:
English

Citation Formats

Rechard, Robert P., Sanchez, Lawrence C., Hadgu, Teklu, Wang, Yifeng, Skinner, Corey, McDaniel, Patrick, Frank, Steve, and Patterson, Micheal. Feasibility of Direct Disposal of Electrorefiner Salt Waste.. United States: N. p., 2016. Web.
Rechard, Robert P., Sanchez, Lawrence C., Hadgu, Teklu, Wang, Yifeng, Skinner, Corey, McDaniel, Patrick, Frank, Steve, & Patterson, Micheal. Feasibility of Direct Disposal of Electrorefiner Salt Waste.. United States.
Rechard, Robert P., Sanchez, Lawrence C., Hadgu, Teklu, Wang, Yifeng, Skinner, Corey, McDaniel, Patrick, Frank, Steve, and Patterson, Micheal. 2016. "Feasibility of Direct Disposal of Electrorefiner Salt Waste.". United States. doi:. https://www.osti.gov/servlets/purl/1397120.
@article{osti_1397120,
title = {Feasibility of Direct Disposal of Electrorefiner Salt Waste.},
author = {Rechard, Robert P. and Sanchez, Lawrence C. and Hadgu, Teklu and Wang, Yifeng and Skinner, Corey and McDaniel, Patrick and Frank, Steve and Patterson, Micheal},
abstractNote = {Abstract not provided.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 2016,
month = 9
}

Conference:
Other availability
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  • Abstract not provided.
  • The experimental breeder reactor (EBR-II) used fuel with a layer of sodium surrounding the uranium-zirconium fuel to improve heat transfer. Disposing of EBR-II fuel in a geologic repository without treatment is not prudent because of the potentially energetic reaction of the sodium with water. In 2000, the US Department of Energy (DOE) decided to treat the sodium-bonded fuel with an electrorefiner (ER), which produces metallic uranium product, a metallic waste, mostly from the cladding, and the salt waste in the ER, which contains most of the actinides and fission products. Two waste forms were proposed for disposal in a minedmore » repository; the metallic waste, which was to be cast into ingots, and the ER salt waste, which was to be further treated to produce a ceramic waste form. However, alternative disposal pathways for metallic and salt waste streams may reduce the complexity. For example, performance assessments show that geologic repositories can easily accommodate the ER salt waste without treating it to form a ceramic waste form. Because EBR-II was used for atomic energy defense activities, the treated waste likely meets the definition of transuranic waste. Hence, disposal at the Waste Isolation Pilot Plant (WIPP) in southern New Mexico, may be feasible. This report reviews the direct disposal pathway for ER salt waste and describes eleven tasks necessary for implementing disposal at WIPP, provided space is available, DOE decides to use this alternative disposal pathway in an updated environmental impact statement, and the State of New Mexico grants permission.« less
  • Argonne National Laboratory has developed a ceramic waste form to immobilize radioactive waste salt produced during the electrometallurgical treatment of spent fuel. This study presents the first results from electron microscopy and durability testing of a ceramic waste form produced from that radioactive electrorefiner salt. The waste form consists of two primary phases: sodalite and glass. The sodalite phase appears to incorporate most of the alkali and alkaline earth fission products. Other fission products (rare earths and yttrium) tend to form a separate phase and are frequently associated with the actinides, which form mixed oxides. Seven-day leach test results aremore » also presented.« less
  • No abstract prepared.