Liquidus temperature and chemical durability of selected glasses to immobilize rare earth oxides waste

Syazwani Mohd Fadzil, Pavel Hrma, Michael J. Schweiger, Brian J. Riley

Research output: Contribution to journalArticle

10 Citations (Scopus)

Abstract

Pyroprocessing is are processing method for managing and reusing used nuclear fuel (UNF) by dissolving it in an electrorefiner with a molten alkali or alkaline earth chloride salt mixture while avoiding wet reprocessing. Pyroprocessing UNF with a LiCl-KCl eutectic salt releases the fission products from the fuel and generates a variety of metallic and salt-based species, including rare earth (RE) chlorides. If the RE-chlorides are converted to oxides, borosilicate glass is a prime candidate for their immobilization because of its durability and ability to dissolve almost any RE waste component into the glass matrix at high loadings. Crystallization that occurs in waste glasses as the waste loading increases may complicate glass processing and affect the product quality. This work compares three types of borosilicate glasses in terms of liquidus temperature (T<inf>L</inf>): the International Simple Glass designed by the International Working Group, sodium borosilicate glass developed by Korea Hydro and Nuclear Power, and the lanthanide aluminoborosilicate (LABS) glass established in the United States. The LABS glass allows the highest waste loadings (over 50 mass% RE<inf>2</inf>O<inf>3</inf>) while possessing an acceptable chemical durability.

Original languageEnglish
Pages (from-to)657-663
Number of pages7
JournalJournal of Nuclear Materials
Volume465
DOIs
Publication statusPublished - 13 Jul 2015

Fingerprint

liquidus
durability
Oxides
Rare earths
Durability
rare earth elements
Glass
Borosilicate glass
oxides
glass
borosilicate glass
Chlorides
Lanthanoid Series Elements
Salts
nuclear fuels
chlorides
Nuclear fuels
salts
Rare earth elements
Temperature

Keywords

  • Crystallization
  • Durability
  • Liquidus temperature
  • Rare earth waste glass

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Materials Science(all)
  • Nuclear Energy and Engineering

Cite this

Liquidus temperature and chemical durability of selected glasses to immobilize rare earth oxides waste. / Mohd Fadzil, Syazwani; Hrma, Pavel; Schweiger, Michael J.; Riley, Brian J.

In: Journal of Nuclear Materials, Vol. 465, 13.07.2015, p. 657-663.

Research output: Contribution to journalArticle

@article{ae8d216708064feaaea5d884141d8f2f,
title = "Liquidus temperature and chemical durability of selected glasses to immobilize rare earth oxides waste",
abstract = "Pyroprocessing is are processing method for managing and reusing used nuclear fuel (UNF) by dissolving it in an electrorefiner with a molten alkali or alkaline earth chloride salt mixture while avoiding wet reprocessing. Pyroprocessing UNF with a LiCl-KCl eutectic salt releases the fission products from the fuel and generates a variety of metallic and salt-based species, including rare earth (RE) chlorides. If the RE-chlorides are converted to oxides, borosilicate glass is a prime candidate for their immobilization because of its durability and ability to dissolve almost any RE waste component into the glass matrix at high loadings. Crystallization that occurs in waste glasses as the waste loading increases may complicate glass processing and affect the product quality. This work compares three types of borosilicate glasses in terms of liquidus temperature (TL): the International Simple Glass designed by the International Working Group, sodium borosilicate glass developed by Korea Hydro and Nuclear Power, and the lanthanide aluminoborosilicate (LABS) glass established in the United States. The LABS glass allows the highest waste loadings (over 50 mass{\%} RE2O3) while possessing an acceptable chemical durability.",
keywords = "Crystallization, Durability, Liquidus temperature, Rare earth waste glass",
author = "{Mohd Fadzil}, Syazwani and Pavel Hrma and Schweiger, {Michael J.} and Riley, {Brian J.}",
year = "2015",
month = "7",
day = "13",
doi = "10.1016/j.jnucmat.2015.06.050",
language = "English",
volume = "465",
pages = "657--663",
journal = "Journal of Nuclear Materials",
issn = "0022-3115",
publisher = "Elsevier",

}

TY - JOUR

T1 - Liquidus temperature and chemical durability of selected glasses to immobilize rare earth oxides waste

AU - Mohd Fadzil, Syazwani

AU - Hrma, Pavel

AU - Schweiger, Michael J.

AU - Riley, Brian J.

PY - 2015/7/13

Y1 - 2015/7/13

N2 - Pyroprocessing is are processing method for managing and reusing used nuclear fuel (UNF) by dissolving it in an electrorefiner with a molten alkali or alkaline earth chloride salt mixture while avoiding wet reprocessing. Pyroprocessing UNF with a LiCl-KCl eutectic salt releases the fission products from the fuel and generates a variety of metallic and salt-based species, including rare earth (RE) chlorides. If the RE-chlorides are converted to oxides, borosilicate glass is a prime candidate for their immobilization because of its durability and ability to dissolve almost any RE waste component into the glass matrix at high loadings. Crystallization that occurs in waste glasses as the waste loading increases may complicate glass processing and affect the product quality. This work compares three types of borosilicate glasses in terms of liquidus temperature (TL): the International Simple Glass designed by the International Working Group, sodium borosilicate glass developed by Korea Hydro and Nuclear Power, and the lanthanide aluminoborosilicate (LABS) glass established in the United States. The LABS glass allows the highest waste loadings (over 50 mass% RE2O3) while possessing an acceptable chemical durability.

AB - Pyroprocessing is are processing method for managing and reusing used nuclear fuel (UNF) by dissolving it in an electrorefiner with a molten alkali or alkaline earth chloride salt mixture while avoiding wet reprocessing. Pyroprocessing UNF with a LiCl-KCl eutectic salt releases the fission products from the fuel and generates a variety of metallic and salt-based species, including rare earth (RE) chlorides. If the RE-chlorides are converted to oxides, borosilicate glass is a prime candidate for their immobilization because of its durability and ability to dissolve almost any RE waste component into the glass matrix at high loadings. Crystallization that occurs in waste glasses as the waste loading increases may complicate glass processing and affect the product quality. This work compares three types of borosilicate glasses in terms of liquidus temperature (TL): the International Simple Glass designed by the International Working Group, sodium borosilicate glass developed by Korea Hydro and Nuclear Power, and the lanthanide aluminoborosilicate (LABS) glass established in the United States. The LABS glass allows the highest waste loadings (over 50 mass% RE2O3) while possessing an acceptable chemical durability.

KW - Crystallization

KW - Durability

KW - Liquidus temperature

KW - Rare earth waste glass

UR - http://www.scopus.com/inward/record.url?scp=84936972102&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=84936972102&partnerID=8YFLogxK

U2 - 10.1016/j.jnucmat.2015.06.050

DO - 10.1016/j.jnucmat.2015.06.050

M3 - Article

VL - 465

SP - 657

EP - 663

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

SN - 0022-3115

ER -