Experience of on-site disposal of production uranium-graphite nuclear reactor
| Autor: | Sergey Gennad’evich Kotlyarevskiy, E. V. Bespala, Elena V. Zakharova, Vyacheslav M. Ermolaev, A. O. Pavliuk, Anna Volkova |
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| Rok vydání: | 2017 |
| Předmět: |
020209 energy
Health Toxicology and Mutagenesis chemistry.chemical_element 02 engineering and technology 01 natural sciences Nuclear decommissioning 010305 fluids & plasmas law.invention Stack (abstract data type) law Nuclear Reactors 0103 physical sciences Nitrogen gas 0202 electrical engineering electronic engineering information engineering Environmental Chemistry Graphite Waste Management and Disposal Radionuclide Waste management General Medicine Uranium Nuclear reactor Pollution Coolant Refuse Disposal chemistry Radioactive Waste Environmental science |
| Zdroj: | Journal of environmental radioactivity. |
| ISSN: | 1879-1700 |
| Popis: | The paper reported the experience gained in the course of decommissioning EI-2 Production Uranium-Graphite Nuclear Reactor. EI-2 was a production Uranium-Graphite Nuclear Reactor located on the Production and Demonstration Center for Uranium-Graphite Reactors JSC (PDC UGR JSC) site of Seversk City, Tomsk Region, Russia. EI-2 commenced its operation in 1958, and was shut down on December 28, 1990, having operated for the period of 33 years all together. The extra pure grade graphite for the moderator, water for the coolant, and uranium metal for the fuel were used in the reactor. During the operation nitrogen gas was passed through the graphite stack of the reactor. In the process of decommissioning the PDC UGR JSC site the cavities in the reactor space were filled with clay-based materials. A specific composite barrier material based on clays and minerals of Siberian Region was developed for the purpose. Numerical modeling demonstrated the developed clay composite would make efficient geological barriers preventing release of radionuclides into the environment. |
| Databáze: | OpenAIRE |
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