首页> 外文OA文献 >Gamma irradiation resistance of an early age slag-​blended cement matrix for nuclear waste encapsulation
【2h】

Gamma irradiation resistance of an early age slag-​blended cement matrix for nuclear waste encapsulation

机译:用于核废料封装的早期矿渣混合水泥基质的γ辐射抗性

代理获取
本网站仅为用户提供外文OA文献查询和代理获取服务,本网站没有原文。下单后我们将采用程序或人工为您竭诚获取高质量的原文,但由于OA文献来源多样且变更频繁,仍可能出现获取不到、文献不完整或与标题不符等情况,如果获取不到我们将提供退款服务。请知悉。

摘要

Irradiation is one of the characteristic conditions that nuclear wasteforms must withstand to assure integrity during their service life. This study investigates gamma irradiation resistance of an earlyage slag cement-based grout, which is of interest for the nuclear industry as it is internationally used for encapsulation of low and intermediate level radioactive wastes. The slag cement-based grout withstands a gamma irradiation dose of 4.77 MGy over 256 h without reduction in its compressive strength; however, some cracking of irradiated samples was identified. The high strength retention is associated with the fact that the main hydration product forming in this binder, a calcium aluminum silicate hydrate (C–A–S–H) type gel, remains unmodified upon irradiation. Comparison with a heat-treated sample was carried out to identify potential effects of the temperature rise during irradiation exposure. The results suggested that formation of cracks is a combined effect of radiolysis and heating upon irradiation exposure.
机译:辐射是核废料在使用寿命期间必须承受的特征性条件之一。这项研究调查了一种基于早期矿渣水泥的水泥浆的耐伽马射线,这在核工业中是很重要的,因为它在国际上被用于封装中低放射性废物。矿渣水泥基水泥浆在256 h内承受的辐射量为4.77 MGy,而抗压强度却没有降低。但是,发现辐照后的样品开裂。高强度保持力与以下事实有关:在该粘合剂中形成的主要水合产物,即硅酸铝钙水合物(CA–S–H)型凝胶,在辐照后仍保持不变。与热处理的样品进行比较,以确定辐射暴露期间温度升高的潜在影响。结果表明,裂纹的形成是辐射照射下辐射分解和加热的综合作用。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
代理获取

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号