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Updated: Jul 20, 2025

Synthesis of Non-uniformly Pr-doped SrTiO3 Ceramics and Their Thermoelectric Properties

Synthesis of Non-uniformly Pr-doped SrTiO3 Ceramics and Their Thermoelectric Properties

Published on: August 15, 2015

评估固体陶废弃物形式的物理化学特性和中心温度

Byeonggwan Lee^1,2, Jung-Hoon Choi¹, Ki Rak Lee¹

¹Korea Atomic Energy Research Institute, 111 Daedeok-daero 989, Yuseong-gu, Daejeon, 34057, Republic of Korea.

|July 31, 2023

概括

废核燃料需要去除90 (Sr-90) 才能有效储存. 研究人员开发了一种稳定的酸 (SrTiO3) 陶废物形式,这对于管理衰变热量和确保安全处置至关重要.

科学领域:

核工程核工程是指核工程.
材料科学材料科学材料科学
废物管理废物管理

背景情况:

废核燃料的处置需要管理来自-137 (Cs-137) 和-90 (Sr-90) 等核体的短期衰变热量.
储存设施的有效利用需要有效地分离和管理这些初级核素.
韩国原子能研究所 (KAERI) 正在开发用于核分离和管理的先进工艺,包括通过降水和蒸来分离核.

研究的目的:

使用酸 (SrTiO3) 陶废物形式将 (Sr) 核化物固定起来.
评估已形成的废物形式的物理化学,放射学和热特性.
评估用于中间储存的Sr废物形式的热行为和安全性,考虑到使用过的核燃料的历史.

主要方法:

通过固态反应方法制备SrTiO3陶废物形式.
物理化学性质的评估,包括机械强度和漏性.
评估放射和热特性,包括根据燃烧和冷却周期估计核化物成分.
使用稳定状态导电方程计算中心线温度.

主要成果:

该SrTiO3废物形式表现出稳定性,良好的机械强度,有利的漏性能和低的热膨胀系数.
评估了放射性和热性特征,同时考虑了核燃料的使用历史.
废物形式的中心线温度随其直径的增加而增加.
对于具有10年冷却周期的燃料产生的SrTiO3废物形式,在所有燃烧条件下,中线温度超过了材料的点,直径为0.275米.

结论:

开发的SrTiO3陶废物形式适用于固定Sr核化物,因为它在中间储存中具有有利的特性.
该研究为处理和储存钢铁废物提供了关键数据,强调了废物形状直径在防止热外流方面的重要性.
了解热行为对于设计安全高效的废核燃料中间储存解决方案至关重要.

关键词:

陶废物形式陶废物形式高级废弃物废弃物高级废弃物核体管理流程核体管理流程钢铁废物形成制造业的废物在SrTiO3O3中使用.废物负担最小化技术的技术.

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