首页> 外文期刊>ACI Materials Journal >Evaluation of high-temperature behavior of sacrificial concrete in nuclear reactor core containment structures
【24h】

Evaluation of high-temperature behavior of sacrificial concrete in nuclear reactor core containment structures

机译:核反应堆堆芯安全壳结构中牺牲混凝土的高温行为评估

获取原文
获取原文并翻译 | 示例
       

摘要

Sacrificial concrete is a cement-based material used for fire protection purposes. It is commonly used as a protective layer in nuclear reactor core containment structures in nuclear power plants. Its purpose is to act as a protection material only. Sacrificial concrete is particularly effective in protecting nuclear reactor core containment because it possesses high temperature stability and high melt capability that can reduce or help avoid the deterioration due to ultra-high temperature exposure from nuclear reactor core accidents or meltdowns. Sacrificial concrete is used in European pressurized reactors (EPRs), as an example, to contain molten core melts by melting a sacrificial concrete layer within the containment, which helps to cool the molten core and assists in avoiding a hot melt on the load-bearing containment structure. The study of performance of sacrificial concrete in ultra-high temperature exposures is in its early stages. To investigate the behavior and properties of sacrificial concrete at the ultra-high temperature of 5430°F (3000°C), numerical modeling simulating the same environment of a nuclear accident is established. Results indicate that the water-cementitious materials ratio (w/cm) and mineral admixtures have a significant impact on compressive strength, water loss, and water content of sacrificial concrete. Mixture proportions presented in this paper possess outstanding spalling resistance and melting behavior. Even at ultra-high temperatures, the sacrificial concrete possesses good melting behavior, and the melt depth of sacrificial concrete increases proportionally with time, which can effectively reduce the detriment of a nuclear accident.
机译:牺牲混凝土是用于防火目的的水泥基材料。它通常用作核电站核反应堆堆芯安全壳结构中的保护层。其目的是仅充当保护材料。牺牲混凝土在保护核反应堆堆芯安全方面特别有效,因为它具有高温稳定性和高熔解能力,可以减少或帮助避免由于核反应堆堆芯事故或熔毁引起的超高温暴露而导致的劣化。例如,在欧洲加压反应堆(EPR)中使用牺牲性混凝土,通过熔化安全壳内的牺牲性混凝土层来容纳熔融的核芯熔体,这有助于冷却熔融的核芯并有助于避免承重时产生热熔体。围护结构。牺牲混凝土在超高温环境下的性能研究尚处于早期阶段。为了研究牺牲混凝土在5430°F(3000°C)的超高温下的行为和性能,建立了模拟核事故同一环境的数值模型。结果表明,水硬性材料的比例(w / cm)和矿物掺合料对牺牲混凝土的抗压强度,失水量和含水量有显着影响。本文提出的混合物比例具有出色的抗剥落性和熔融行为。即使在超高温下,牺牲混凝土也具有良好的熔化性能,并且牺牲混凝土的熔化深度会随时间成比例增加,从而可以有效减少核事故的危害。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

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