Tetiana Lavrova, Oleg Voitsekhovych, Sergey Todosiienko Ukrainian Hydrometeorological Institute, Department of Environment Radiation Monitoring Ukraine, Kiev lavrova@uhmi.org.ua o.voitsekhovych@gmail.com
Background PridneprovskyChemical Plant (PChP) in Dneprodzerzhinsk is legacy of U-production facilities in Ukraine where the ambitious State Remediation program is under development Large area (100 ha) with gamma dose rate > 0,5 µsv/h 5- high contaminat. buildings (1 µsv/h -1 msv/h) Several U-tailings and number of hot spots Several ponds containing high contaminated sludge (U-238, Ra-226, Th-230) High chemical pollution of soils and groundwaters
Specific features of the Site contamination Large amount of radioactive residues containing high activity of Uranium, Th-230 and Ra-226 are still containing in the tanks and equipment. Large amount of U-production residues in fine dispersed materials are presents in spills near some apparatus and leaked pipelines inside of the most contaminated buildings and at the territory High activity concentrations of Th-230 and Ra-226 (irom10-50 Bq/g to 400-600 Bq/g) were identified in many places of Buildings #103, #104, 2b and also in the sludge materials. The characteristics of Uranium, Th-230 and Ra-226 in the different buildings and surrounding environment (soils, aerosols, river water and groundwater) are versus of type of the U-and Thcontaining Ores and also technology used at the PChP industrial site This study is part of site characterization and remediation planning
U-extraction technology used for different type of U-ores U-ore residues from extraction of mineral materials from UA and countries of CIS, Bq/g Uranium Ore from UA, Ore warehouse Building 1 Base S storage Phosphate-Uranium Ore from Kazakhstan Ore warehouse Building A U-238 Th-230 Ra-226 0.4-3.5 40-600 1.5-22.0 Crusher (2 stages) Building 2, 3 Wet grinding Building 4, 5 Wet grinding, re-pulping Building 1B Leaching, sorption, desorption, neutralisation Building 2Б, 2В, 2Е Residues from extraction of the Phosphate U-Ore (Kazakhstan), Bq/g Raw uranium from countries of CEC Pulp thickening Building 28 Leaching, sorption, Desorption, neutralisation Building 6 Thorium removal Building 104 Rare earths concentrates Building 95 Nitrofos Building 77 U-238 Th-230 Ra-226 10-3200 10-150 10-1700 Pulp to tailings facility Extraction, re-extraction, filtration, calcination -- Building 103 Phosphogypsum to tailings facility U 3 O 8
Analytical laboratory UHMI includes High efficient gamma, alpha and LLC spectrometry devices as well as basic radiochemical and environment sample preparation facilities
Environmental samples measurement Gamma Spectrometry 4 HPGeSemiconductor Detectors Type -GEM, GWL, GMX ORTEC, BE5030 -CANBERRA Measurement - 234 Th ( 238 U), 230 Th 235 U, 226 Ra, 228 Ra, 210 Pb, 228 Th, 40 K, 137 Cs, 241 Am and ets. The calibration: by the soil standard sample SRM (IAEA-434), IAEARGU-1 and IAEA-RGTh-1 Alpha Spectrometry U-238,234, Th-232, 230, 228 and Po-210 LS Spectrometry Gross alpha-, beta-activity, U-238+ 234, Ra-226
Counts Simplified methods for U-Thseries radionuclidesdetermination in waters (UMF-2000, and LLC) 40 30 20 10 UMF-2000 V - 0.5 L, Tracer 232 U - 0.135 Bq Т=12000 s 238 U, 4198 kеv 234 U, 4773 kev 232 U, 5320 kev 0 175 225 275 325 Channel Counts 15 10 5 СЕА-01 V - 0.5 L, Tracer 232 U - 0.135 Bq Т=15000 s 238 U, 4151 kev 238 U, 4198 kev 235 U, 4398 kev 234 U, 4721 kev 234 U, 4773 kev 232 U, 5264 kev 232 U, 5320 kev Отсчеты / канал 10 8 6 4 Спектр 234+238 U Т изм. =1500сек (UO 2 (NO 3 ) 2 в 5ml ТБФ +15 ml ЖС-1) 238 U (4198 кэв) + 234 U (4775 кэв) 0 600 700 800 900 Channel 2 0 0 100 200 300 400 500 600 700 800 900 1000 1100 Номер канала
Complex of U-containing ore materials milling, grinding, settling purification and final U-extraction-calcination( Building 103) and Thextraction and purifications (Buildings 2b and 104) µsv/h
µsv/h 1000 Building 103, Level 1 and Level 2 Detailed gamma survey was supported by EC-UA partnership project
Specific Feature of radiological hazards in the Building 104 is high specific activities of Th-230 identified in the spill and extraction columns Data UHMI & Ecomonitor, 2016 Samples Activity concentration, Bq/g Pb-210 Ra-226 Th-230 Th-232 S104-01 19.3 27.6 574 4.7 S104-02 0.8 2.6 250 2.3 S104-07 21.4 10.2 253 2.9 S104-09 30.8 7.9 35.2 0.3 Specific reference activity concentration levels for ( U-Th decay series) --Th-230 1 Bq/g
Radiological Hazards containing materials with high activity concentrations of U, Ra-226 and Th-230 around sludge ponds Selected hot spots to be removed around ponds 230 and 220
Sludge materials in sedimentation pond 230 (cell 12) are high contaminated by Th-230 (15-240 Bq/g) and toxic metals (Arsenic) Other materials in the pond 220 can be released from regulatory control 220/2 220/3 220/1 230/3 230/2 230/ 1
Dnieper River Dredging of the bottom sediment in Konoplyanka river may significantly improve ecological situation at the surrounding areas Konoplyanka River PChP UPLS
Contaminants from the PChPULS Inlet to the River Konoplyanka and mainly deposited in the bottom sediment Contaminated water inflow to the Dnieper reservoir шар грунту, см Колонка 1_2004 Бк кг-1 0 50 100 150 200 250 300 350 400 450 0 U-238 Ra-226 5 10 15 20 Th-228 Cs-137 Pb-210 25 шар грунту, см Колонка 2_2012 Бк кг-1 0 50 100 150 200 250 300 350 400 450 0 U-238 Ra-226 10 Th-228 Cs-137 20 Pb-210 30 40 50 шар грунту, см Колонка 1_2003 Бк кг-1 0 50 100 150 200 250 300 350 400 450 500 0 U-238 Ra-226 5 Th-228 Cs-137 10 15 20 Pb-210 60 25
Dniepr reservoir has accumulate contaminants from PChP site. Impact of the PChP site via aquatic pathways are very low Lake Somovka р. Самара Inventory of Aerosol fallout 0.0 20.0 40.0 60.0 80.0100.0120.0140.0160.0180.0200.0220.0240.0260.0280.0 2005 2008 Radionuclides in bottom sediment 1995 1985 1975 1965 1955 1945 1994 1976 U-238 mbq/cm2 year 0 10 0 100 200 300 400 500 600 700 Bq kg -1 1935 Щільність накопичення Pb-210, мбк/(см 2 рік) 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 Layer of bottom sediment, cm 20 30 U-238 40 Ra-226 Th-228 50 Cs-137 Pb-210 60 70 60 km downstream from artificial mouth 80 Konoplyanka River Проммайданчик колишнього ВО ПХЗ 90 роки 2005 1995 1985 1975 1965 1955 1945 1935 1994 1976 Pb-210 mbq/cm2 year 2008
The State Program (2016-2017) is under implementation The program is developed to provide Safe management at the legacy site, to support functions of the SE Barrier (Operator) ensure its functions such as: Site Safety management (radiological and nonradiological), surveillance and monitoring Preparedness to further and ongoing remediation activities to be implemented in the frame of EC projects (2017-2020) Provision security and Radiation protection at the site Coordination and support of the site investigation and actions for remediation strategy planning (national and international) Public communication and data management 17
In the Frame of EC project planned for 2017-2018 the Emergency Measures to Improve Safety and Stability at the most contaminated facilities will be implemented. The tasks are following: To fix or collect high contaminated dispersed materials in the buildings of the former U-extraction facilities (103 and 104) To stabilize the most contaminated buildings (sealing windows and walls), Repair tailings covers, decontaminate some hot spots, establish fences and more strict radiation protection control actions. It may help significantly reduce the immediate radiological risk until implementation of remediation actions (including establishment of boundaries) To raise awareness on and near the site about the conditions of the site and measures to mitigate the risk.
Specific tasks to be implemented Development of special enterprise for decontamination, recycling and possible re-processing of the wastes to be generated during remediation Vacuum and wet decontamination techniques may be used and tested for its possible application for selected premises which high contaminated by dispersed residues and spills. Decontamination technologies used in EU and USA for clean-up and radioactive waste management of the high contaminated (U-Ra) dispersed materials
Acknowledgement We appreciate very much to EC funds making possible to complete basic site characterization studies in the frame of EC-UA U4.01/10G also project partners (FACILIA AB, WISMUT GEO), JSO- UA) as well as Ministry of Energy and Coal Industry and Regulatory body of Ukraine on deep concern and efforts to support this study. Also we appreciate IAEA for sufficient consulting and financial support making possible to present this report on the NORM Symposia Thank you very much with hope on further cooperation to be developed