A wet-oxidation procedure of radioactive waste resin and waste concentrated liquid for 3 H and 14 C analysis
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A wet‑oxidation procedure of radioactive waste resin and waste concentrated liquid for 3H and 14C analysis Yan‑Jun Huang1 · Jing Jiang2 · Gui‑Yin Guo1 · Fan Zeng1 · Xin‑Hua Liu2 Received: 30 June 2020 © Akadémiai Kiadó, Budapest, Hungary 2020
Abstract 3 H and 14C are two of the principal isotopes that should be considered in the characterization of radioactive waste from the nuclear power plant. In this paper, an analytical method of 3H and 14C in radioactive waste resin and waste concentrated liquid with a wet-oxidation process was presented, which allowed us to obtain both samples of 3H and 14C simultaneously. The chemical yields were optimized based on an orthogonal experiment with fresh resin. The analytical precision and the minimum detectable concentration (MDC) were provided. The chemical yield of 14C during the process for resin was about 96.8%. There was no significant difference between the analytical results of 14C with the wet-oxidation method and those with the oxygen-bomb combustion method. The MDCs of activity of 3H and 14C were 41 Bq/gww and 1.3 Bq/gww for waste resin, and 1.3 Bq/gww and 0.02 Bq/gww for waste concentrated liquid. The method was applied to determine the radioactivity concentrations in the waste from a typical nuclear power plant. It was shown that the averaged concentrations of 3H and 14 C in the radioactive waste resin were 6134 Bq/gww and 2724 Bq/gww, and the averages in waste concentrated liquid were 104.7 Bq/gww and 27.3 Bq/gww, respectively. Keywords Wet oxidation · Waste resin · Waste concentrated liquid · 3H · 14C
Introduction Safety requirement is a critical issue during radioactive treatment, processing, disposal of solid wastes from the nuclear power plants [1]. It usually includes waste resins, concentrated liquids, waste filter cartridge, and other technical wastes. A detailed characterization of the radioactivity in the waste is of great concern which would provide effective support such as to determine whether it meets the requirements of clearance level or acceptance criteria of radioactive waste storage facilities[2–4]. 3 H and 14C are two principal radionuclides that produced and released from nuclear power plants [5]. It was reported that the amount of 14C in solid waste generated from a typical light–water reactor (1000 MW(e) installed * Yan‑Jun Huang [email protected] 1
Suzhou Nuclear Power Research Institute, Co. Ltd., Suzhou 215004, People’s Republic of China
Nuclear and Radiation Safety Center, Ministry of Ecology and Environment, Beijing 102445, People’s Republic of China
2
capacity) is about 647.5 GBq/a, significantly higher than that released through gaseous and liquid effluent with the amount about 129 GBq/a and 1.3 GBq/a respectively[5, 6]. 3 H also accounts for a certain proportion of different types of solid waste. According to the effluent monitoring report of the US nuclear power plant [7], taking the data from the report of Shearon Harris nuclear power plant in 2015 as an example, the proportion of 3H in waste resin and dry solid waste wa
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