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Status of Activities on Rehabilitation Of Radioactively Contaminated Facilities and the Site of Russian Research Center ''Kurchatov Institute''
This paper describes the program, the status, and the course of activities on rehabilitation of radioactively contaminated facilities and the territory of temporary radioactive waste (radwaste) disposal at the Russian Research Center ''Kurchatov Institute'' (RRC KI) in Moscow as performed in 2001-2002. The accumulation of significant amounts of radwaste at RRC KI territory is shown to be the inevitable result of Institute's activity performed in the days of former USSR nuclear weapons project and multiple initial nuclear power projects (performed from 1950's to early 1970's). A characterization of RRC KI temporary radwaste disposal site is given. Described is the system of radiation control and monitoring as implemented on this site. A potential hazard of adverse impacts on the environment and population of the nearby housing area is noted, which is due to possible spread of the radioactive plume by subsoil waters. A description of the concept and project of the RRC KI temporary radwaste disposal site is presented. Specific nature of the activities planned and performed stems from the nearness of housing area. This paper describes main stages of the planned activities for rehabilitation, their expected terms and sources of funding, as well as current status of the project advancement. Outlined are the problems faced in the performance and planning of works. The latter include: diagnostics of the concrete-grouted repositories, dust-suppression technologies, packaging of the fragmented ILW and HLW, soil clean-up, radioactive plume spread prevention, broad radiation monitoring of the work zone and environment in the performance of rehabilitation works. Noted is the intention of RRC KI to establish cooperation with foreign, first of all, the U.S. partners for the solution of problems mentioned above
Experimental study of power density mapping in reactors by redistribution of fissionable material
Almost total smoothing of the energy release along the radius of a heterogeneous reactor
International Conference Nuclear Energy for New Europe 2003 Development of Fast Helium Cooled Reactors in Russia
ABSTRACT Nuclear energy of the 21 century will be characterized by the use in its structure of fast reactors wherein nuclear fuel breeding is accomplished along with thermal reactors. A combined use of high-temperature gas cooled reactors on thermal (HTGR) and fast (BGR) neutrons may prove to be one of good solutions to the problem of providing fuel for the future nuclear energy. The high helium temperature at the outlet of such reactors allows both electricity generation and using heat for various processes, such as hydrogen production. The paper presents results of the analysis of efforts on development of fast helium cooled reactor concepts previously undertaken in Russia. Advantages of fast helium cooled reactors (BGR) over fast liquid metal cooled reactors are demonstrated. Various BGR concepts are analyzed. One of the concepts consists in attaining the maximum breeding ratio through the use of a modular reactor with a small core containing 239 Pu without breeder material (the plutonium core reactor). In the second concept, an increase in the reactor power while maintaining the fuel breeding parameters is accomplished in a reactor with a multiplutonium core based on placement of several plutonium cores in a certain periodic structure inside a common uranium blanket. In the third concept, the reactor power is increased through an increase of the core volume using plutonium diluted with 238 U (MOX fuel). The possibility of using in BGR a single-circuit scheme of converting heat to electricity with a gas turbine along with the conventional two-circuit scheme in a steam-turbine cycle is demonstrated. Design development efforts performed in Russia allowed designing a BGR-300 pilot fast helium reactor with electric power level of 300 MW. Main parameters of this reactor are presented. A point is made of the promise offered by international cooperation in development and application of high-temperature helium cooled reactor both on thermal (HTGR) and fast (BGR) neutrons for nuclear energy of the 21 century. 102.
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