Feasibility Study of Solidification for Low-Level Liquid Waste Generated by Sulfuric Acid Elution Treatment of Spent Ion Exchange Resin
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概要
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We studied cement-like solidification process for low-level liquid waste with relatively high levels of radioactivity that contains a high concentration of sodium sulfate. For this type waste, it is important that the sulfate ion should not dissolve from the solid waste because it forms ettringite on reaction with minerals in the concrete of the planned repository, and this leads to cracking during repository storage. It is also preferable that the pH of the pore water of the solid waste be low, because the bentonite of the repository changes in quality on exposure to alkaline solution. Therefore, the present solidification process has two procedures: conversion into insoluble sulfate from sodium sulfate (CIS) and formation of low pH cement-like solid (FLS). In the CIS procedure, BaSO4 precipitation occurs with addition of Ba(OH)2•8H2O to the liquid waste. In the FLS procedure, silica fume and blast furnace slag are added to the liquid waste containing BaSO4 precipitate. We show the range of appropriate Ba/SO4 molar ratio is from 1.1 to 1.5 in the present solidification process by leaching tests for some kinds of solid waste samples. The CIS reaction yield is over 98% at a typical CIS condition, i.e. Ba/SO4 molar ratio=1.3, reaction temperature=60°C, and time=3 hr.
- 一般社団法人 日本機械学会の論文
著者
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ASANO Takashi
Power & Industrial Systems R & D Laboratory, Hitachi, Ltd.
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KAWASAKI Tooru
Hitachi Works, Hitachi-GE Nuclear Energy, Ltd.
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HIGUCHI Natsuko
Nuclear Power Division, The Kansai Electric Power Co., Inc.
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HORIKAWA Yoshihiko
Nuclear Power Division, The Kansai Electric Power Co., Inc.