scholarly journals Determination of Optimum Dimension for the High Radioactive Waste Storage Container

2014 ◽  
Vol 26 (13) ◽  
pp. 4049-4051 ◽  
Author(s):  
Geun-Ho Kim ◽  
Jong-Hwan Lee ◽  
Kwan-Seong Jeong ◽  
Dongjun Hyun ◽  
Byung-Seon Choi ◽  
...  
Author(s):  
Nazirzhon T. Buriev ◽  
Dzhamshed A. Abdushukurov ◽  
Tjalle T. Vandergraaf

The National Radioactive Waste Storage and Disposal Site was established in 1959 in the Faizabad region approximately 50 km east of the capital, Dushanbe. The site is located on the southern flank of the Fan Mountains facing the Gissar Valley in a sparsely populated agricultural area, with the nearest villages located a few km from the site. The site was initially designed to accept a wide range of contaminated materials, including obsolete smoke detectors, sealed radioactive sources, waste from medical institutions, and radioactive liquids. Between 1962 and 1976, 363 tonnes and 1146 litres of material, contaminated with a range of radionuclides were shipped to the site. Between 1972–1980 and 1985–1991, ∼4.8 × 1014 and 2 × 1013 Bq, respectively, were shipped to the site. An additional 7 × 1014 Bq was shipped to the site in 1996. Partly as a result of the dissolution of the former Soviet Union, the disposal site had fallen into disrepair and currently presents both an environmental hazard and a potential for the proliferation of radionuclides that could potentially be used for illicit purposes. Remediation of the disposal site was started in 2005. New security fences were erected and a new superstructure over an in-ground storage site constructed. A central alarm monitoring and observation station has been constructed and is now operational. The geology, flora, and fauna of the region have been documented. Radiation surveys of the buildings and the storage and disposal sites have been carried out. Samples of soil, surface water and vegetation have been taken and analyzed by gamma spectrometry. Results show a slight extent of contamination of soils near the filling ports of the underground liquid storage container where a Cs-137 concentration of 2.3 × 104 Bq/kg was obtained. Similar values were obtained for Ra-226. Radiation fields of the in-ground storage site were generally <1 μSv/h with 8% exceeding this value. Neutron radiation levels at the same location were also low with a few readings exceeding 10 μSv/h. The volume of liquid waste is estimated to be ∼140 m3. Most of the activity appears to be associated with the sediments in the tank. Suggestions are presented for the immobilization of the liquid wastes and long-term monitoring of the site and the surrounding territory.


1988 ◽  
Vol 127 ◽  
Author(s):  
I. Plećaš ◽  
J. Drljača ◽  
A. Perić ◽  
A. Kostadinović

ABSTRACTTo assess the safety for disposal of radioactive waste cement composite, the leaching of Cs-137, Co-60, Mn-54 and Sr-85 from a waste composite into a surounding fluid has been studied [1, 2]. Leaching tests were carried out in accordance with a method recommended by IAEA |2, 3|. Determination of retardation factors, KF, and coefficients of distribution, kd, using a simplified mathematical model for analysing the migration of radionuclides, has been developed. |4, 7, 8|Results presented in this paper are examples of results obtained in a 10 year mortar and concrete testing project, which will influence the design of the engineered trenche system for future central Yugoslavian radioactive waste storage center. |7, 8|.


1991 ◽  
Vol 93 (3) ◽  
pp. 611-635 ◽  
Author(s):  
Richard W. Stoffle ◽  
Michael W. Traugott ◽  
John V. Stone ◽  
Paula D. McIntyre ◽  
Florence V. Jensen ◽  
...  

Science ◽  
1995 ◽  
Vol 268 (5215) ◽  
pp. 1262-1263
Author(s):  
Ed Fuller

2020 ◽  
Vol 11 (2) ◽  
pp. 17-24
Author(s):  
D. N. Vlasov ◽  
◽  
D. N. Zamaskin ◽  
O. O. Kaminsky ◽  
A. V. Kamorny ◽  
...  

The article discusses one of today’s challenges, namely, the decommissioning of nuclear power facilities. It summarizes the experience in the decommissioning of radioactive waste storage facilities belonging to RosRAO’s Murmansk department branch of the Northwest Territorial District providing detailed overview of pre-decommissioning activities, as well as the decommissioning operations themselves, relevant technology and technical equipment applied. Pre-decommissioning stage involved large-scale efforts (2011—2015) on accumulated RW identifi cation and its inventory taking, as well as a comprehensive engineering radiation survey. Decommissioning projects have been developed and approved, a state environmental examination has been carried out with a Sanitary and Epidemiological Statement on compliance with state sanitary and epidemiological rules and regulations issued by FMBA of Russia. The paper presents the practice of constructing some engineering structures to provide additional safety and security of RW storage facilities during their dismantlement. Particular attention was paid to the problems associated with the use of special equipment.


2021 ◽  
Vol 2021 (1) ◽  
pp. 95-107
Author(s):  
Victoria Olegovna Zharkova ◽  
Yana Yuryevna Karasyova ◽  
Elena Iosifovna Lysakova ◽  
Elena Vasilievna Zakharova

Author(s):  
E.V. Kuzmin ◽  
A.V. Kalakutskiy ◽  
M.A. Tarasov ◽  
A.A. Morozov

The paper presents a concept for disposal of Class 2 and Class 3 radioactive waste in existing workings and chambers in the underground uranium mines of the Priargunsky Industrial Mining and Chemical Union PJSC with isolation of radioactive waste storage chambers using paste backfilling made with processed uranium ore materials and sealing of cracks in host rock by injection consolidation. The need is shown to enhance the strength of radioactive waste containers to increase the number of tiers in the storage blocks to make better use of the available chamber space. Data is provided on the forecast hydrogeological conditions in deep levels (up to 1000 m) of Mine No.6.


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