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A Temperature Distribution Model for a Nuclear Waste Prototype Repository

机译:核废料原型库的温度分布模型

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摘要

The disposal of spent nuclear fuel and other nuclear waste is one of the main contentionsrnconcerning the nuclear power industry. The design and construction of therndeep geological spent nuclear fuel repository is very sophisticated process, which includesrnmany types of particular analyses. One of the important partial studies of arnnuclear waste repository can be called thermal dimensioning, a basic simulation ofrnthermal conditions depending on the structure and size of the repository. The importantrnparameters for repository layout are thermal properties of the host rock and barrier,rnheat generated by a nuclear waste, number of disposal boreholes and their spacing.rnThe design of repository is determined by thermal criteria, which place limits onrnthe maximum temperature that can allowed in the barrier surrounding the boreholes.rnIn this paper the finite element model is used to show the influence of heat transportrnproperties of the rock and barrier, spacing of boreholes on the maximum temperaturernachieved in the repository. The setting up and application of the proper model is therncrucial factor for the results validity. The model represents an structure of tunnels andrnboreholes with canisters disposing in the different time. The segment of the modelrnconsists of many segments, which include one quarter of borehole and neighbouringrncrystalline rock. This model is more accurate than the infinite model of the repository,rnwhere assumption is, that all canisters are disposed in the same time.
机译:乏核燃料和其他核废料的处置是核电行业的主要争论之一。深层地质乏核燃料库的设计和建设是非常复杂的过程,其中包括许多类型的特定分析。核废料储存库的重要局部研究之一可以称为热尺寸,这是根据储存库的结构和大小对热工况进行的基本模拟。储存库布局的重要参数是主岩和屏障的热性质,核废料产生的热量,处置钻孔的数量及其间距。储存库的设计由热学标准​​确定,这些标准对可允许的最高温度进行了限制。本文采用有限元模型来显示岩石和屏障的传热特性,井眼间距对储层中达到的最高温度的影响。正确模型的建立和应用是结果有效性的关键因素。该模型表示隧道和钻孔的结构,并在不同的时间放置碳罐。该模型的段由许多段组成,其中包括四分之一的钻孔和邻近的结晶岩。该模型比存储库的无限模型更为精确,在这种情况下,假设所有容器都在同一时间放置。

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