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THERMAL MODELING OF HIGH-LEVEL NUCLEAR WASTE DISPOSAL IN A SALT REPOSITORY

机译:盐矿库中高水平核废料处置的热模拟

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摘要

Salt formations have received recent attention for geologic disposal of heat-generating, high-level nuclear waste (HLW). Existing investigations are summarized and expanded upon using analytical and numerical models to investigate simulated temperatures in the salt after emplacement of HLW. Analytical modeling suggests that temperature variations near canisters will be smooth, indicating that the system can be approximated by a coarsely discretized numerical model. Two multidimensional parameter studies explore canister configuration using characteristics from (a) defense HLW and (b) spent nuclear fuel (SNF) waste. Numerical modeling was conducted for a disposal concept consisting of emplacement of waste canisters on the floor of drifts and covering each with salt backfill. Results indicate that waste forms with U.S. Department of Energy (DOE) waste characteristics can be easily configured to maintain simulated temperatures far below 200℃ at spacings as close as 0.3 m (~1 ft), the minimum feasible spacing that could practically be achieved. For SNF waste packaged into canisters with heat loads of 1500 or 1000 W with canister spacing of 6 m (~20 ft) and 3 m (~10 ft), respectively, simulated temperatures can be maintained below 200℃; much higher maximum temperatures would result for designs with higher canister heat loads and smaller spacings. These results indicate that from a thermal loading perspective, in-drift disposal of HLW in salt deposits is feasible for DOE-managed waste as long as the maximum temperature is managed through proper selection of canister heat loads and spacings. The results will aid in the design of potential future field tests to confirm this conclusion.
机译:盐层在产生热量的高水平核废料(HLW)的地质处置方面受到了最近的关注。使用分析和数值模型对高放废物放置后盐中的模拟温度进行了总结并扩展了现有研究。分析模型表明,碳罐附近的温度变化将是平滑的,这表明该系统可以通过粗糙离散的数值模型来近似。两项多维参数研究使用(a)国防高级别武器和(b)废核燃料(SNF)废物的特征探索了碳罐的配置。对废物处理概念进行了数值模拟,包括将废物罐放置在排水槽的地板上,并用回盐盐覆盖它们。结果表明,具有美国能源部(DOE)废物特征的废物形式可以轻松配置,以在接近0.3 m(〜1 ft)的间距(实际上可以达到的最小可行间距)下维持模拟温度远低于200℃。对于包装在热负荷为1500或1000 W,罐间距分别为6 m(〜20 ft)和3 m(〜10 ft)的罐中的SNF废物,模拟温度可以保持在200℃以下;对于具有较高罐热负荷和较小间距的设计,将导致更高的最高温度。这些结果表明,从热负荷的角度看,只要通过适当选择碳罐的热负荷和间距来控制最高温度,就可以在DOE管理的废物中对盐矿中的高放废物进行漂移处理是可行的。结果将有助于设计潜在的未来现场测试,以证实这一结论。

著录项

  • 来源
    《Nuclear Technology》 |2014年第3期|294-307|共14页
  • 作者单位

    Los Alamos National Laboratory, P.O. Box 1663 MS T003, Los Alamos, New Mexico;

    Los Alamos National Laboratory, P.O. Box 1663 MS T003, Los Alamos, New Mexico;

    Los Alamos National Laboratory, P.O. Box 1663 MS T003, Los Alamos, New Mexico,California State University, Fullerton;

    Los Alamos National Laboratory, P.O. Box 1663 MS T003, Los Alamos, New Mexico,Neptune and Company, Inc.;

    Los Alamos National Laboratory, P.O. Box 1663 MS T003, Los Alamos, New Mexico;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
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  • 入库时间 2022-08-18 00:43:17

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