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Title: A Study on Vitrification for LLW Radioactive Wastes - 16235

Abstract

Ash and ion exchange resin wastes to be vitrified were considered among various radioactive wastes in the Japanese nuclear industry. The appropriate glass composition for the waste is calculated using the computer program. The glass composition is systematically studied using a ternary diagram, considering viscosity, electrical conductivity, and durability. The optimized glass composition based on calculated parameters of vitrification process and the convenience of mixing wastes is selected for crucible experiment. Since differences between calculated values and measured values may occur upon evaluation of glass formulations using glass formulation computer simulation program, the calculated glass formulations should be verified through experiments on a laboratory scale for more meticulous development of glass formulations. For the follow-up development of glass formulations, several glass formulations are planned to be developed. The candidate glasses for treatment of ash and ion exchange resin were melted and fabricated using reagents, respectively. The chemicals were weighed out to produce the desired batch compositions and mixed thoroughly and then put into clay crucibles for melting. Next, the crucibles were introduced into an electric furnace at 1,150 deg. C in the ambient atmosphere and pressure with occasional stirring by a quartz rod. A hold time of 1 hour wasmore » introduced to promote homogenization. Finally, the melted material was poured on a graphite plate to be rapidly cooled. The viscosities of all fabricated glasses were in the desired range. After rapid cooling, the micro-structure of the glasses was analyzed using the SEM. They exhibited amorphous structure with good homogeneity. (authors)« less

Authors:
; ;  [1]; ; ; ;  [2]
  1. Central Research Institute, Korea Hydro and Nuclear Power (Korea, Republic of)
  2. Yokohama Engineering Center, IHI Corporation (Japan)
Publication Date:
Research Org.:
WM Symposia, Inc., PO Box 27646, 85285-7646 Tempe, AZ (United States)
OSTI Identifier:
22838099
Report Number(s):
INIS-US-19-WM-16235
TRN: US19V1292083454
Resource Type:
Conference
Resource Relation:
Conference: WM2016: 42. Annual Waste Management Symposium, Phoenix, AZ (United States), 6-10 Mar 2016; Other Information: Country of input: France; 4 refs.; available online at: http://archive.wmsym.org/2016/index.html
Country of Publication:
United States
Language:
English
Subject:
12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; CLAYS; COMPUTERIZED SIMULATION; ELECTRIC CONDUCTIVITY; GLASS; GRAPHITE; HARDNESS; ION EXCHANGE; LOW-LEVEL RADIOACTIVE WASTES; MELTING; MICROSTRUCTURE; NUCLEAR INDUSTRY; SCANNING ELECTRON MICROSCOPY; SERVICE LIFE; VISCOSITY; VITRIFICATION; WEAR RESISTANCE

Citation Formats

Hwang, Young Hwan, Jo, Hyun-Jun, Kim, Cheon-Woo, Oniki, Toshiro, Tachibana, Takahiro, Nabemoto, Toyonobu, and Endo, Yoshihiro. A Study on Vitrification for LLW Radioactive Wastes - 16235. United States: N. p., 2016. Web.
Hwang, Young Hwan, Jo, Hyun-Jun, Kim, Cheon-Woo, Oniki, Toshiro, Tachibana, Takahiro, Nabemoto, Toyonobu, & Endo, Yoshihiro. A Study on Vitrification for LLW Radioactive Wastes - 16235. United States.
Hwang, Young Hwan, Jo, Hyun-Jun, Kim, Cheon-Woo, Oniki, Toshiro, Tachibana, Takahiro, Nabemoto, Toyonobu, and Endo, Yoshihiro. 2016. "A Study on Vitrification for LLW Radioactive Wastes - 16235". United States.
@article{osti_22838099,
title = {A Study on Vitrification for LLW Radioactive Wastes - 16235},
author = {Hwang, Young Hwan and Jo, Hyun-Jun and Kim, Cheon-Woo and Oniki, Toshiro and Tachibana, Takahiro and Nabemoto, Toyonobu and Endo, Yoshihiro},
abstractNote = {Ash and ion exchange resin wastes to be vitrified were considered among various radioactive wastes in the Japanese nuclear industry. The appropriate glass composition for the waste is calculated using the computer program. The glass composition is systematically studied using a ternary diagram, considering viscosity, electrical conductivity, and durability. The optimized glass composition based on calculated parameters of vitrification process and the convenience of mixing wastes is selected for crucible experiment. Since differences between calculated values and measured values may occur upon evaluation of glass formulations using glass formulation computer simulation program, the calculated glass formulations should be verified through experiments on a laboratory scale for more meticulous development of glass formulations. For the follow-up development of glass formulations, several glass formulations are planned to be developed. The candidate glasses for treatment of ash and ion exchange resin were melted and fabricated using reagents, respectively. The chemicals were weighed out to produce the desired batch compositions and mixed thoroughly and then put into clay crucibles for melting. Next, the crucibles were introduced into an electric furnace at 1,150 deg. C in the ambient atmosphere and pressure with occasional stirring by a quartz rod. A hold time of 1 hour was introduced to promote homogenization. Finally, the melted material was poured on a graphite plate to be rapidly cooled. The viscosities of all fabricated glasses were in the desired range. After rapid cooling, the micro-structure of the glasses was analyzed using the SEM. They exhibited amorphous structure with good homogeneity. (authors)},
doi = {},
url = {https://www.osti.gov/biblio/22838099}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Jul 01 00:00:00 EDT 2016},
month = {Fri Jul 01 00:00:00 EDT 2016}
}

Conference:
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