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就拟议中的尤卡山高放废物处置库而言,¹⁴C和²²⁸Ra的意义。

Significance of 14C and 228Ra in terms of the proposed Yucca Mountain high-level radioactive waste repository.

作者信息

Moeller Dade W, Ryan Michael T, Cherry Robert N, Sun Lin-Shen C

机构信息

Dade Moeller & Associates Inc., 257 River Island Road, New Bern, NC 28562, USA.

出版信息

Health Phys. 2006 Sep;91(3):238-48. doi: 10.1097/01.HP.0000214658.69442.44.

DOI:10.1097/01.HP.0000214658.69442.44
PMID:16891899
Abstract

C and Ra are two of the radionuclides that have either been identified as being potentially significant in terms of releases from the proposed Yucca Mountain high-level radioactive waste repository, or are specifically cited for consideration and evaluation in the regulations promulgated by the U.S. Nuclear Regulatory Commission. The purpose of this study was to estimate the concentrations and associated doses for these two radionuclides, if released under conditions of a scenario assumed to apply to a repository containing some of the features of the one proposed at Yucca Mountain, NV, and to compare these estimates to the regulatory limits for that facility. For C, the postulated condition was that an annual fractional release of 10 of its total remaining inventory occurs beginning at 10,000 y after repository closure. For Ra, the same fractional release rate was assumed, but in this case it was presumed to occur when the Ra inventory was projected to reach a maximum at more than 10 y after repository closure. The estimated concentrations and doses were, in turn, compared to the concentration limit, specified in the Ground Water Protection Standards (GWPSs) in the case of Ra, or derived, in the case of C, on the basis of the regulatory dose rate limit. Due to the small inventory of C in the waste, and its short half-life relative to the performance period evaluated, its estimated concentration in the ground water would be slightly more than 4% of the derived GWPS. Due to the relatively small initial inventory of Th, the precursor of Ra, and the correspondingly small quantities of higher atomic number actinides that could, through decay, produce additional quantities of Th, its estimated concentration in the ground water would be less than 3% of the GWPS, leaving the remaining portion of the limit for potential contributions from Ra. At the same time, however, it must be recognized that, in this case, the regulations require that any contributions of naturally occurring Ra and Ra already present in the ground water must be included in the determination of compliance. If this is done, the total concentration of Ra, combined with the naturally occurring concentration of Ra, would be about 10.5% of the limit. In a similar manner, the committed doses due to the annual consumption of each of these two radionuclides in ground water and food, produced in the local biosphere, were evaluated in terms of the Individual Protection Standard (IPS). Based on these analyses, the estimated effective dose for C, using the coefficients in Federal Guidance Report (FGR) No. 13, was 4.15 muSv y, less than 3% of the IPS. For Ra, the comparable estimate at the time of maximum inventory, excluding in this case the contributions from naturally occurring Ra and Ra, was 7.39 muSv y, representing about 5% of the IPS. Based on the value assumed for the fractional release rate (10 y), it was concluded that neither C nor Ra will be significant in terms of either the applicable GWPS or the IPS. While it was recognized that, due to the time spans involved, these analyses were primarily an academic exercise, it is believed that the perspectives and accompanying insights are useful.

摘要

碳-14((^{14}C))和镭-226((^{226}Ra))是两种放射性核素,它们要么被认定为从拟议的尤卡山高放废物处置库释放时可能具有重大意义,要么在美国核管理委员会颁布的法规中被特别提及以供考虑和评估。本研究的目的是估算这两种放射性核素在假设适用于具有内华达州尤卡山拟建处置库某些特征的处置库情景下释放时的浓度及相关剂量,并将这些估算值与该设施的监管限值进行比较。对于(^{14}C),假定条件是在处置库关闭10000年后开始,其剩余总量的年释放分数为(10^{-6})。对于(^{226}Ra),假定相同的释放分数率,但在这种情况下,假定在处置库关闭10多年后镭库存预计达到最大值时发生释放。然后,将估算的浓度和剂量分别与镭的《地下水保护标准》(GWPSs)中规定的浓度限值进行比较,对于(^{14}C),则根据监管剂量率限值得出的浓度限值进行比较。由于废物中(^{14}C)的存量较少,且相对于评估的性能期其半衰期较短,其在地下水中的估算浓度将略高于推导得出的GWPS的4%。由于镭的前体钍-230((^{230}Th))初始存量相对较小,以及相应数量较少的可通过衰变产生额外钍量的高原子序数锕系元素,其在地下水中的估算浓度将低于GWPS的3%,这就留下了镭潜在贡献的限值剩余部分。然而,与此同时必须认识到,在这种情况下,法规要求在确定合规性时必须纳入天然存在的镭以及地下水中已有的镭的任何贡献。如果这样做,镭的总浓度加上天然存在的镭浓度,将约为限值的10.5%。以类似方式,根据《个人防护标准》(IPS)评估了当地生物圈中地下水中和食物中这两种放射性核素每年消耗所导致 的待积剂量。基于这些分析,使用第13号《联邦指导报告》(FGR)中的系数,(^{14}C)的估算有效剂量为(4.15)微希沃特/年,低于IPS的3%。对于(^{226}Ra),在最大库存时的可比估算值(在这种情况下不包括天然存在的镭和镭的贡献)为(7.39)微希沃特/年,约占IPS的5%。基于假定的释放分数率值((10^{-6})),得出结论:无论是(^{14}C)还是(^{226}Ra),就适用的GWPS或IPS而言都不会具有重大意义。虽然认识到由于所涉及的时间跨度,这些分析主要是一项学术活动,但相信这些观点及相关见解是有用的。

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