scholarly journals A study on waterproof capabilities of the bentonite-containing engineered barrier used in near surface disposal for radioactive waste

2021 ◽  
Vol 7 (1) ◽  
pp. 37-42
Author(s):  
Cao Nguyen Luu ◽  
Ba Tien Nguyen ◽  
Thu Hien Doan Thi ◽  
Van Chinh Nguyen ◽  
Huu Anh Vuong

Study of nuclear fuel cycle in Vietnam at the aspect of domestic production, the exploitation and process of uranium ore were began. These processes generated large amounts of radioactive waste overtiming. The naturally occurring radioactive material and technologically enhanced radioactive material (NORM/TENORM) waste, which would be large, needs to be managed and disposed reasonably by effectivemethods. It was therefore very important to study the model of the radioactive waste repository, where bentonite waterproofing layer would be applied for the low and very low level radioactive waste in disposal site. The aim of this study was to obtain the preliminary parameters for low-level radioactive waste disposal site suitable with the conditions of Vietnam. The investigation of the ratio between soil and bentonite was interested in the safety of the uranium tailings disposal site. The experiments with some layers of waterproofing material with the ratio of soil and bentonite are 75/25; 50/50; 25/75 were carried out to test the moving of uran nuclide through these waterproofing material layers. Waterproofing layers containing bentonite combined with soil were compacted into PVC pipes. One end of the plastic tube is sealed, the other end is embedded in a solution containing uranium nuclide. Analyzing the uranium content in each layers (0,1 cm) of material pipe is to determine the uranium nuclide adsorption from solution into the material in the different ratios at the different times: 1, 2 and 3 month. The results showed that the calculated average speeds of the migration of uranium nuclide into the soil- bentonite layer are 5.4.10-10, 5.4.10-10 and 3,85.10-10 m/s and thickness waterproofing layer (for 300 years) are 4,86 m, 4,86 m and 3,63 m for layer with the ratio of soil and bentonite are 75/25; 50/50; 25/75 respectively

2010 ◽  
Vol 27 (3) ◽  
pp. 231-239 ◽  
Author(s):  
Michael J. Wilkins ◽  
Francis R. Livens ◽  
David J. Vaughan ◽  
Jonathan R. Lloyd ◽  
Ian Beadle ◽  
...  

2019 ◽  
Vol 197 ◽  
pp. 174-183 ◽  
Author(s):  
Abdel-Aal M. Abdel-Karim ◽  
Ahmed A. Zaki ◽  
Waheed Elwan ◽  
Mohamed R. El-Naggar ◽  
Mahmoud M. Gouda

1984 ◽  
Vol 44 ◽  
Author(s):  
D. R. Mackenzie ◽  
R. E. Barletta ◽  
J. F. Smalley ◽  
C. R. Kempf ◽  
R. E. Davis

AbstractThe Sheffield low-level radioactive waste disposal site, which ceased operation in 1978, has been the focus of modeling efforts by the NRC for the purpose of predicting long-term site behavior. To provide the NRC with information required for its modeling effort, a study to define the source term for tritium in eight trenches at the Sheffield site has been undertaken. Tritium is of special interest since significant concentrations of the isotope have been found in groundwater samples taken at the site and at locations outside the original site boundary. Previous estimates of tritium site inventory at Sheffield are in wide disagreement. In this study, the tritium inventory in the eight trenches was estimated by reviewing the radioactive shipping records (RSRs) for waste buried in these trenches. It has been found that the tritium shipped for burial at the site was probably higher than previously estimated. In the eight trenches surveyed, which amount to roughly one half the total volume and activity buried at Sheffield, approximately 2350 Ci of tritium from non-fuel cycle sources were identified.


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