Vitrification processes of simulated cesium sorbing zeolite waste

Research output: Contribution to journalArticle

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Abstract

A large amount of high-activity-level water (HALW) contaminated with mainly radioactive cesium has been generated at Fukushima Dai-ichi Nuclear Power Plant (NPP), and a decontamination system for the HALW has been operated. For decontamination of the HALW, modified chabazite-type zeolite has been used as a sorbent, and the amount of the cesium bearing zeolite waste is still increasing. One of conditioning options for the zeolite waste is vitrification into borosilicate glass waste form, which is considered to be a promising option for the back-end of nuclear fuel cycle. For the purpose of the optimum treatment and disposal, the effects of the vitrification conditions on the total performance are required to be evaluated quantitatively. In this study, vitrification tests of simulated zeolite waste, which is the same type of zeolite used in the decontamination system at Fukushima Dai-ichi NPP and is sorbing non-radioactive cesium, were examined to evaluate the homogeneity of glass products and the volume reduction ratio (glass specific volume to zeolite specific volume) with respect to the temperature of melting process. Furthermore, the volatilization loss of cesium was evaluated as a function of the additive loading, processing temperature and processing time. The results showed that the glass products are in a completely amorphous state and their volume reduction ratios were around 0.4 at any vitrification condition above 1100 °C. In addition, a certain amount of the volatilization loss occurred under the conditions of high additive loading and high temperature.

Original languageEnglish
Pages (from-to)497-502
Number of pages6
JournalProgress in Nuclear Energy
Volume108
DOIs
Publication statusPublished - Sep 1 2018

Fingerprint

vitrification
Vitrification
cesium
Cesium
zeolite
Decontamination
Water levels
Vaporization
Glass
Density (specific gravity)
Nuclear power plants
water level
Bearings (structural)
glass
nuclear power plant
volatilization
Borosilicate glass
Nuclear fuels
Processing
Sorbents

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering
  • Safety, Risk, Reliability and Quality
  • Energy Engineering and Power Technology
  • Waste Management and Disposal

Cite this

Vitrification processes of simulated cesium sorbing zeolite waste. / Kimura, Ryou; Inagaki, Yaohiro; Idemitsu, Kazuya; Arima, Tatsumi.

In: Progress in Nuclear Energy, Vol. 108, 01.09.2018, p. 497-502.

Research output: Contribution to journalArticle

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