Evaluation of thermal stability in deep geological repository and nuclear criticality safety of spent nuclear fuel vitrified in iron phosphate glass

被引：7

作者：

Lee, Cheong Won ^{[1
,2
]}

Shin, Sung Gyun ^{[1
,2
]}

Kye, Yong Uk ^{[3
]}

Heo, Jong ^{[1
,2
]}

机构：

[1] Pohang Univ Sci & Technol POSTECH, Div Adv Nucl Engn, Pohang 37673, Gyeongbuk, South Korea

[2] Pohang Univ Sci & Technol POSTECH, Dept Mat Sci & Engn, Pohang 37673, Gyeongbuk, South Korea

[3] Pohang Accelerator Lab, Pohang 37673, Gyeongbuk, South Korea

来源：

ANNALS OF NUCLEAR ENERGY | 2020年 / 136卷

基金：

新加坡国家研究基金会;

关键词：

Vitrification; Nuclear criticality safety; Deep geological repository; WASTE; BEHAVIOR; DESIGN;

D O I：

10.1016/j.anucene.2019.107055

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Iron phosphate glasses with low melting temperatures of similar to 1300 degrees C were developed to immobilize spent nuclear fuels (SNFs). The glasses have densities of similar to 3.15 g/cm(3) and glass transition temperatures of similar to 540 degrees C that are high enough to endure the temperatures in geological repositories. The waste loading of CeO2 in the glass was similar to 21.92 wt%, which corresponds to similar to 30.38 wt% of UO2 at the same molar ratio. Normalized elemental releases from the product consistency test were well below the regulated limit of 2 g/m(2). Effective neutron multiplication factor k(eff) was 0.755, which is below nuclear criticality safety regulation (k(eff) = 0.95). Vitrified SNF occupies one-eleventh of the repository space compared to direct disposal of the same amount of UO2, excluding left-over low-level wastes. (C) 2019 Elsevier Ltd. All rights reserved.

引用

页数：6

共 28 条

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