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METHODOLOGY FOR DETERMINATION OF RADIOASSAY PROPERTIES FORRH-TRU WASTE

机译:测定RH-TRU废料的放射分析特性的方法

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The Battelle Columbus Laboratories Decommissioning Project (BCLDP) decontamination anddecommissioning activities will generate approximately 25 cubic meters of remote-handledtransuranic (RH-TRU) wastes, which are planned for ultimate disposal at the Waste IsolationPilot Plant (WIPP). For WIPP disposal, the isotopic inventory of the waste must becharacterized to demonstrate compliance with applicable limits. The BCLDP has developed amethodology that combines limited assay, knowledge of the processes generating the waste, anda dose/weight-to-curie evaluation to determine the isotopic characterization of the waste.The BCLDP methodology determines the isotopic content for an identified TRU waste stream bya combination of (1) representative waste stream sample analyses, (2) application of Oak RidgeIsotope Generation and Depletion (ORIGEN2) code values for isotopes expected in spent nuclearfuel but not represented by the sample analyses, and (3) assessment of cesium (Cs)-137 contentof a payload container based on external radiation field measurements and calculation of TRUisotopic content using a ratio of radionuclides based on known Cs-137 content. The measuredisotopic distribution (gamma emitters) of a waste stream is combined with values determinedthrough the conservative application of the ORIGEN2 to account for all isotopes. External doserates for 1 millicurie of an isotopic mix are modeled for different packaging configurations.Field sort charts permit determining the quantity of radionuclides in each waste package frommeasured weights and dose rates. The inventory of Cs-137 is determined for each drum basedon external radiation field measurement using a high-purity germanium detector. Cs-137 is usedas an indicator of TRU content of a drum based on the ratio of radionuclides. The methodologydeterminations are verified on an approved, periodic basis by gamma and/or alpha spectroscopy.The methodology includes the conservative estimation of measurement errors and assumptionsused to determine a total uncertainty that is bounding for the methodology.This methodology is consistent with worker safety principles and is optimal for the BCLDP, asmall quantity site with limited waste and resources. In addition, given the small fraction of RHTRUwastes to be disposed of at the WIPP, and its insignificant impact on the long-termperformance of the repository, the use of sophisticated assay techniques for RH-TRU waste isneither warranted nor necessary. The BCLDP methodology is a simple system that meets theintent of the governing regulations for the WIPP.
机译:Battelle哥伦布实验室退役项目(BCLDP)的去污和退役活动将产生约25立方米的远距离超铀(RH-TRU)废物,这些废物计划最终在废物隔离试点工厂(WIPP)进行处置。对于WIPP处置,必须对废物的同位素清单进行表征,以证明其符合适用的限值。 BCLDP已开发出一种方法学,该方法结合了有限的测定方法,对产生废物的过程的了解以及对剂量/重量到居里的评估来确定废物的同位素特征.BCLDP方法通过以下方法确定已识别的TRU废物流的同位素含量: (1)有代表性的废物流样品分析,(2)应用Oak Ridge同位素产生和耗竭(ORIGEN2)编码值来预测用过的核燃料中预期但未通过样品分析表示的同位素,以及(3)铯(Cs)评估的组合-137的有效载荷容器的含量是基于外部辐射场测量以及使用基于已知Cs-137含量的放射性核素比率计算的TRU同位素含量。将废物流的测得同位素分布(伽马发射体)与通过保守应用ORIGEN2确定的值结合起来,以说明所有同位素。针对不同包装结构模拟了1毫同位素混合物的外部剂量率。现场分类图允许根据测量的重量和剂量率确定每个废物包装中的放射性核素数量。使用高纯度锗探测器根据外部辐射场测量结果确定每个感光鼓的Cs-137存量。 Cs-137用作基于放射性核素比率的感光鼓TRU含量的指标。该方法的测定在批准的定期基础上通过γ和/或α光谱法进行验证。该方法包括对测量误差的保守估计和用于确定该方法有局限性的总不确定性的假设,该方法与工人安全原则和最适用于BCLDP,少量废物和资源有限的站点。此外,鉴于在WIPP处置的RHTRU废物数量很少,并且对处置库的长期性能影响不大,因此,不保证也没有必要使用复杂的RH-TRU废物测定技术。 BCLDP方法是一个简单的系统,可以满足WIPP的管理法规的意图。

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