Dismantling of Active Drains in the Technological Enclosures of the MR Reactor

Atomic Energy - The results of the dismantling of the active drain system and the decontamination of technological enclosures of the loop installations of the MR reactor, which is being...     

Preparations for decommissioning the MR research reactor at the Russian Science Center Kurchatov institute

The preparations of the MP research loop reactor for decommissioning are described. After final shutdown in 1993, a system of measures to ensure the required level of nuclear and radiation safety for the complex was implemented and a concept and fundamental program for decommissioning the reactor were developed. The variant DECON was taken as the base variant for decommissioning — immediate staged disassembly of structures and equipment, including disassembly of in-vessel structures of the RFT predecessor reactor which are stored in a central room of the reactor. The main results of the work performed to normalize the radiation conditions in the central room and to examine the safety-and-control system repository in this room are presented. __________ Translated from Atomnaya énergiya, Vol. 104, No. 5, pp. 259–264, May, 2008.     

Decomposition of radioactive methyl iodide in an electric discharge field

The possibility of using electric discharge for removing radioactive iodine in the form of volatile organic compounds from air-gas streams was examined. In an electric discharge field, at the methyl iodide concentration in the range from 0.9 to 19 mg l^?1, relative humidity within 48–90%, and linear flow velocity of 0.5–3.5 cm s^?1, the decontamination factor characterizing the methyl iodide decomposition is ≥1.4 × 10⁵.     

Testing of experimental fuel elements for VVÉR-1000 reactors in MR to high fuel burnup

Conclusions The results of testing in a multipurpose reactor and post-irradiation examinations indicate satisfactory performance of the fuel element for the VVÉR-1000, which is designed for a 3-year run. In addition to the computational data, the experimental data were used to substantiate the performance of fuel elements when fuel burnup is increased and atomic power plants are switched from the VVÉR-1000 to a 3-year cycle (with an average burnup of 40 MW-day/kg).I. V. Kurchatov Institute of Atomic Energy. Translated from Atomnaya Énergiya, Vol. 72, No. 2, pp. 116–120. February, 1992.     

Decommissioning of nuclear and radiation-hazardous objects of the russian science center “Kurchatov Institute”

Data are presented on research reactors which form the experimental base used for research in radiation materials science, neutron physics, solid-state physics, and other directions in science and technology. The characteristic features of the decommissioning of research reactors are analyzed. The results of work on the decommissioning of reactors and spent-fuel and radioactive-waste repositories are presented. 3 figures, 2 tables, 12 references. Translated from Atomnaya énergiya, Vol. 87, No. 3, pp. 180–189, September, 1999.     

Experience in international collaboration in the development of preliminary plans for decommissioning nuclear research facilities at the Russian science center Kurchatov institute

The joint work performed by specialists at the Russian Science Center Kurchatov Institute, VT Nuclear Services, and Serso Assurance/RWE NUKEM on the development of preliminary plans for decommissioning nuclear research facilities at the Russian Science Center Kurchatov Institute is described. Special attention is focused on using modern methodology and foreign experience in planning such work taking account of local conditions.     

A Laser System for Real-Time Measurement of the 129I and NO2 Concentrations in a Spent Nuclear Fuel Reprocessing Medium

A laser system was developed for real-time detection of the global radionuclide ¹²⁹I and NO₂ during spent nuclear fuel reprocessing. This system was used for determining the concentrations of these substances in a gas stream under actual conditions of nitric acid dissolution of spent nuclear fuel at the Khlopin Radium Institute, Research and Production Association. The tests showed that the laser system is suitable for measuring both the ¹²⁹I and NO₂ concentrations directly in the gas phase during spent nuclear fuel reprocessing (this is essential for monitoring this process and controlling the dissolution cycle safety) and in the gases emitted by radiochemical enterprises. The sensitivity with respect to ¹²⁹I, achieved with the laser system developed, also makes it suitable for real-time monitoring of ¹²⁹I and NO₂ at the maximum permissible concentration (MAC) level. This will allow evaluation of the environmental condition of air in the working areas of radiochemical enterprises, as well as in residential areas.     

Combined processing scheme of WWER-1000 spent nuclear fuel: 1. Thermochemical breaking-up of fuel claddings and voloxidation of fuel

Within the framework of the development of a combined scheme for processing WWER-1000 spent nuclear fuel, head operations such as chemical breaking-up of fuel cladding and voloxidation of the fuel with removal of volatile fission products were studied experimentally.