Estimation of aquatic dilution factor for liquid effluent discharges from Kaiga Generating Station using tritium as a tracer

T. Reji, R. Joshi, T. Ajith, Sanyam Jain, M. Vishnu, I. Saradhi, A. Vinodkumar
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Abstract

Very low-level radioactive liquid effluents much below the approved discharge limits are discharged to Kadra reservoir after dilution with condenser cooling water at Kaiga Generating Station. In addition, further dilution occurs from the discharge point to the nearest public utilization point in Kadra reservoir (Hartuga). The dilution obtained in Kadra reservoir is estimated by simultaneous measurements of tritium at the discharge point and at Hartuga. The on-site measurement indicates a dilution factor of 12.2 ± 2.4 for tritium. A dilution factor of 13.3 ± 3.4 was obtained using aquatic dispersion model.
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用氚作示踪剂估算海贺电站液体出水水中稀释系数
远低于批准排放限值的极低放射性液体流出物经Kaiga发电站的冷凝器冷却水稀释后排放到Kadra水库。此外,从排放点到Kadra水库(Hartuga)最近的公共利用点发生进一步稀释。通过在排放点和Hartuga同时测量氚来估计Kadra水库中获得的稀释。现场测量表明,氚的稀释系数为12.2±2.4。采用水生分散模型得到的稀释系数为13.3±3.4。
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Theme 8. Emergency preparedness and response Theme 2. Radiation Safety and Protection in Nuclear Facilities Theme 1. Foundation Topics on Radiation Protection Philosophy and Risk Estimates Theme 7. Existing Exposures Theme 5. Nuclear instrumentation and system development
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