I-129 Waste Form Using Bi-Zn-P-Oxide Glass

被引：0

作者：

Yang, Jae Hwan ^{[1
]}

Shin, Jin Myeong ^{[1
]}

Park, Jang Jin ^{[1
]}

Park, Hwan Seo ^{[1
]}

机构：

[1] Korea Atom Energy Res Inst, Taejon 305353, South Korea

来源：

3RD INTERNATIONAL CONFERENCE ON ASIAN NUCLEAR PROSPECTS (ANUP2012) | 2013年 / 39卷

关键词：

I-129; AgX; waste form; low melting; Bi2O3-P2O5; glass; NA2O-BI2O3-TIO2-P2O5; GLASSES; PHOSPHATE-GLASSES; STRUCTURAL ROLE; BISMUTH; BI2O3;

D O I：

10.1016/j.egypro.2013.07.201

中图分类号：

TE [石油、天然气工业]; TK [能源与动力工程];

学科分类号：

0807 ; 0820 ;

摘要：

I-129 is a problematic nuclide generated from the recycling of spent fuel by pyroprocess. Gaseous form of radiogenic iodine is trapped by using silver exchanged zeolite (AgX) at Korea Atomic Energy Research Institute (KAERI). We developed the low melting temperature glass system based on Bi2O3-P2O5 composition. Various additives were added to modify glass properties. We found that ingots containing AgI are formed with ZnO, CaCO3, MgO, and Na2CO3 at around 600 degrees C Analysis of microstructure and chemical durability revealed that AgI was encapsulated by glass matrix and formation of AgI compound is meaningful in fabricating iodine waste form. (C) 2013 The Authors. Published by Elsevier Ltd.

引用

页码：151 / 158

页数：8

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