Contribution of RT-1 Radiochemical Plant to the Tritium Contamination in the Vicinity of Mayak Production Association

IF 0.9 Q4 CHEMISTRY, INORGANIC & NUCLEAR
Yu. G. Mokrov
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Abstract

Archive data (1970–2024) on the results of monitoring the tritium content of surface liquid radioactive waste (LRW) storage reservoirs (special radioactive waste repositories) and of groundwater in the vicinity of the Mayak Production Association are analyzed. The tritium contamination existing today was formed before the 1970s and was initially accumulated (a) in V-2 reservoir (Kyzyl-Tash), which operated as a reservoir for recirculating direct-cooling of industrial uranium–graphite reactors (PUGRs) in case of failure of uranium slug cladding; (b) in V-9 (Karachay) and V-17 (Staroye Boloto) reservoirs, which were used for storage of intermediate-level tritium-containing liquid waste; (c) in groundwater as a result of tritium seepage from the reservoirs. After putting into operation the RT-1 radiochemical plant (1977), the major fraction of tritium was accumulated in a new LRW type, tritium condensate, which was stored in V-17 reservoir. The contaminated groundwater filtering from V-17 reservoir was discharged only into an inlet of V-10 reservoir of the Techa Cascade of Reservoirs (TCR). The maximal rate of tritium discharge was estimated at 0.11 TBq/year, and the specific activity of tritium in the TCR water, at 2 Bq/L. In the 2020s, the tritium discharge into the atmosphere from the RT-1 plant was ~34 TBq, which was ~2800 times lower than the maximum permissible discharge prescribed for the whole enterprise. The mean value of the annual effective dose from all the pathways of tritium intake by Ozyorsk inhabitants was 0.26 μSv, and the maximal value was 0.49 μSv, which is ~2000 times lower than the dose limit of 1 mSv for the population. The tritium emissions and discharges from the RT-1 plant are negligible and exert virtually no radiation impact on the population.

Abstract Image

RT-1 辐射化学厂对马雅克生产协会附近氚污染的影响
分析了玛雅克生产协会附近地表液态放射性废物储存库(特殊放射性废物储存库)和地下水氚含量监测结果的档案数据(1970-2024 年)。目前存在的氚污染是在 20 世纪 70 年代之前形成的,最初积聚在 (a) V-2 储存库(Kyzyl-Tash)中,该储存库作为工业铀-石墨反应堆(PUGRs)的再循环直接冷却储存库,以防铀块包层失效;(b) V-9(Karachay)和 V-17(Staroye Boloto)蓄水池中,这两个蓄水池用于储存中 等量级的含氚液体废物; (c) 地下水中,因为氚从蓄水池中渗出。RT-1 辐射化学厂投入运行(1977 年)后,氚的主要部分积聚在一种新的低放射性废物--氚冷凝液中,该冷凝液储存在 V-17 水库中。从 V-17 水库过滤出来的受污染地下水只排入特查梯级水库(TCR)的 V-10 水库入口。据估计,氚的最大排放率为 0.11 TBq/年,TCR 水体中氚的比活度为 2 Bq/L。2020 年代,RT-1 工厂向大气排放的氚约为 34 TBq,比整个企业规定的最大允许排放量低约 2800 倍。奥济奥尔斯克居民从所有途径摄入氚的年有效剂量平均值为 0.26 μSv,最大值为 0.49 μSv,比居民的剂量限值 1 mSv 低约 2000 倍。RT-1 工厂的氚排放和排出量可以忽略不计,对居民几乎没有辐射影响。
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来源期刊
Radiochemistry
Radiochemistry CHEMISTRY, INORGANIC & NUCLEAR-
CiteScore
1.30
自引率
33.30%
发文量
51
期刊介绍: Radiochemistry  is a journal that covers the theoretical and applied aspects of radiochemistry, including basic nuclear physical properties of radionuclides; chemistry of radioactive elements and their compounds; the occurrence and behavior of natural and artificial radionuclides in the environment; nuclear fuel cycle; radiochemical analysis methods and devices; production and isolation of radionuclides, synthesis of labeled compounds, new applications of radioactive tracers; radiochemical aspects of nuclear medicine; radiation chemistry and after-effects of nuclear transformations.
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