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Minor actinide waste disposal in deep geological boreholes

机译:在深部地质钻孔中处理少量act系元素废物

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摘要

The purpose of this investigation was to evaluate a waste canister design suitable for the disposal of vitrified minor actinide waste in deep geological boreholes using conventional oil/gas/geothermal drilling technology. The nature of minor actinide waste was considered, paying particular attention to nuclides whose decay energy and half lives were of relative significance to the minor actinide waste as a whole. Thermal Analysis was performed based on a reference borehole design, by Ian C. Hoag. The strategy of the thermal analysis is aimed at finding peak temperatures within the configuration, paying particular attention to the heat transfer under deep geological conditions in the air gap between the canister and the borehole. A first order economic analysis was made to compare the designed canister emplacement costs to that of intact spent fuel. The results of this analysis show that three minor actinide nuclides dominate heat generation after ten years cooling: Cm-244, Am-241, and Am-243 account for 97.5% of minor actinide decay heat. These three nuclides plus Np-237 account for 99% of the minor actinide mass. The thermal analysis was based on an irretrievable canister design, consisting of a 5 meter long synroc waste form, with minor actinides loaded to 1% wt, an outer radius of 15.8 cm and inner annular radius of 8.5 cm. Filling the annulus with a vitrified technetium and iodine waste form was found to be feasible using a multi-stage emplacement process. This process would only be required for three of the fifty boreholes because technetium and iodine have low heat generations after 10 years cooling. The suggested borehole waste form has a maximum centerline temperature of 349C. The costs of drilling boreholes to meet the demand of 100,000MT of PWR waste are estimated to be 3.5% of the current nuclear waste fund, or about $9.6/kg of original spent fuel.
机译:这项研究的目的是评估一种废物罐设计,该废物罐设计适用于使用常规石油/天然气/地热钻探技术处理深层地质钻孔中的玻璃化次act化物废物。考虑了次act系元素废物的性质,尤其要注意其衰变能量和半衰期对整个次act系元素废物具有相对重要性的核素。热分析是根据Ian C. Hoag的参考井眼设计进行的。热分析的策略旨在发现构型内的峰值温度,尤其要注意深地质条件下碳罐与井眼之间的气隙中的传热。进行了一级经济分析,以比较设计的碳罐安装成本和完整的乏燃料成本。分析结果表明,十年冷却后,三种次act系元素核素占主导地位:Cm-244,Am-241和Am-243占次act系元素衰变热的97.5%。这三种核素加上Np-237占次要act系元素质量的99%。热分析基于不可回收的罐设计,该罐设计为5米长的Synroc废料形式,微量minor系元素含量为1%wt,外部半径为15.8 cm,内部环形半径为8.5 cm。发现采用玻璃化em和碘废料形式填充环带是可行的,可采用多阶段安置工艺。因为tech和碘在冷却10年后发热量低,所以只需要对五十个钻孔中的三个钻孔进行此过程。建议的钻孔废料形式的最高中心线温度为349℃。满足100,000吨压水堆废物需求的钻孔成本估计占当前核废料基金的3.5%,约合每千克原始乏燃料9.6美元。

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    Sizer Calvin Gregory;

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  • 年度 2006
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  • 原文格式 PDF
  • 正文语种 eng
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