[en] An overview is given of the characteristics of the experimental facilities and experiments in the Russian Federation: the HTGR neutron-physical investigation facilities ASTRA and GROG; facilities for fuel, graphite and other elements irradiation; and thermal hydraulics experimental facilities. The overview is presented in the form of copies of overhead sheets

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[en] There are more than 20 nuclear power reactors in operation in Russia, which have been operated over 10 years. Operational time of I and C systems of those NPPs is about 30 years, though the lifetime of individual parts of I and C systems is limited by 10-15 years. I and C systems were designed in 60-70-th in accordance with the existing regulations and available technical solutions. Obsolescence of those I and C systems require the reconstruction of existing systems. There are considerations that don't allow to perform equipment replacement one-to-one but require to modernize I and C systems at NPP. (author)

[en] Reasons for instrumentation and control systems of nuclear power plants(NPP) modernization, general approach to modernization activity and current practice of operating NPP modernization are described. 7 refs, 1 tab

[en] This paper presents on the developments of the gas turbine modular helium reactor (GT-MHR) at the Russian OKB Mechanical Engineering {now called as Joint Stock Company Afrikantov OKBM}. The international GT-MHR project was started in 1995 by MINATOM {now called ROSATOM} of Russia and the General Atomics Company (GA) of the US, with Framatome (France) and Fuji Electric (Japan) joining later. In 1997 the GT-MHR concept design was developed. A review conducted by experts in Russia and the US, along with other international experts from Russia, the US, Japan, Germany and France, was successful and concluded that there were no insurmountable obstacles to its implementation. A major part of the design work is being conducted by Russian entities with project participants from the US (GA, ORNL, EPRI) contributing with the development of the plant design concept, the transfer of technology, providing computer analysis codes and the sharing of Fort Saint Vrain operating experience. Currently, project activities and funding are focused on developing the fuel, the helium turbo-machinery, the development and verification of engineering analysis codes and fission product transport codes and the validation of these codes. The ideas and applications covered in this session related to coated particle fuel are all novel or beyond novel, but are important examples suggesting flexible reactor development strategy, waste management, and nuclear non-proliferation. (author)

[en] A large amount of weapons grade plutonium has been currently accumulated in the world. These stock-piles of accumulated plutonium are potentially hazardous because of the possibility of its unpermitted proliferation with subsequent manufacturing and use in nuclear weapons. From this point of view, the problem of the plutonium disposition is urgent. On the other hand, plutonium is an extremely valuable energy product, and should be used efficiently. The concept of burning WGPu in reactor power plants for electricity production is the official Russian position, and is considered as a long-term solution by existing power plants modification as well as with new reactor technologies development. Operating VVERs-1000 and BN-600 are some of the candidates to involve of WGPu in their fuel cycle, but the advantages of Gas Cooled High Temperature Reactors as GT-MHR allow to consider this type of reactor as a surplus WGPu consumer in the nearest future (2010). The inherent safety characteristics of the GT-MHR make it well suited to the mission of WGPu disposition. Because of the high burnup and no breeding of new plutonium, the GT-MHR consumes circa 90 % of the initially charged Pu-239. A single GT-MHR plant consisting of four reactor modules of 600 MWt power each can achieve this level of destruction for 50 tonnes of WGPu with concurrent electricity generation of circa 46 GW·year over its design lifetime. In contrast, only 50 % of initial charged plutonium is consumed in LWR with electricity generation of circa 25 GW·year. Discussion between General Atomics (GA) of United States and the Russian Ministry of Atomic Energy (MINATOM), in the summer of 1994, led to an agreement on a jointly funded design and development program for the GT-MHR, presented in a GA paper at this meeting. The program is initially focused on the burning of weapons plutonium that becomes available from dismantled nuclear weapons. The long term goal is to utilize the same design for commercial applications - using uranium fuel. This program took advantage of existing technologies and facilities in the US and Russia, but right from the beginning left the door open for broader international cooperation. Accordingly, in January 1996, FRAMATOME from France, Europe, has joined the ongoing effort and in April 1997 FUJI ELECTRIC from Japan joined the program. The program is proceeding well. A conceptual design of GT-MHR has been completed in October 1997. Several Russian laboratories, design organizations are participating with GA, FRAMATOME and FUJI ELECTRIC. Significant improvements in the power conversion system design are a clear example of the benefit of the cooperative effort. Further work needs to be done to confirm fuel and components prior to full deployment, etc,, providing ample opportunities for international cooperation in many areas

[en] Nuclear power plant (NPP) with VPBER-600 reactor is a station of new generation. The specified term of reactor plant operation is 60 years and taking into account that the proposed term of starting the first power unit is on the turn of centuries one can definitely state that for Russia conditions VPBER-600 is a plant of 21 century. Such far removed term for NPP now in the stage of development as it can seem does not put the problems of modernization as first order tasks. But open-quotes...who does not think about future lives in the past.close quotes It is that the NPP instrumentation and control (I ampersand C) systems are in the most degree subjected to the influence of factors which favor their modifications. These factors can be arbitrarily divided into two groups: (1) inner factors, i.e. changes (failures, aging, etc) in I ampersand C components as well as changes dictated by technological reasons (change of equipment composition, control algorithms, operation modes); (2) outer factors, i.e. intensive development of information technologies and rapid improvement of electronic components. This presentation addresses the problem of modernization of the safety instrumentation for this next generation facility, and the research effort it will entail. The system is designed to allow for modernization, and the relatively easy adoption of new instrumentation and technology as it becomes available

[en] The lifetime of nuclear power plants (NPP) always exceeds the operational time of Instrumentation and Control (I and C) systems. Ageing of I and C equipment in NPPs have many aspects. Research of these aspects is being performed in OKB Mechanical Engineering. Under condition of fast development of I and C systems and applying more stringent safety requirements, modernization of the equipment irrespective of its operational condition is getting important. However, an equipment of I and C systems operated in Russia was designed and manufactured applying highest requirements for a reliability of their work during its whole operational time. Therefore, in many cases it is not necessary to replace them in spite of expiration of their specified lifetime. During operation this equipment is maintained in a proper operation condition by a special service procedures stipulated by its development. When the equipment lifetime approaches to its end, lifetime extension for the certain period should be considered. (author)

[en] In 1989-90 the Supervision Body approved the new safety regulations for nuclear power plants. The operating plants do not always completely satisfy them and a great amount of work to develop operating power units up to the conditions required is necessary. This paper describes briefly the main changes made in monitoring, control and protection systems of nuclear power reactors to increase the reactor safety. The following fields are presented in the paper: General status of the NPP control and safety systems and instrumentation in USSR; sensors; electronic equipment; actuators improvement; qualification tests. (author). 3 figs

[en] Possibility of GT-MHR spent fuel storage during long time without additional processing is discussed in this paper. Spent fuel elements discharged from this reactor type are ideal waste forms for permanent disposal in a geologic repository. The graphite fuel elements and the ceramic coatings on the fuel particles are as-manufactured engineered barriers that provide excellent near field containment of radionuclides and minimize reliance on the waste package and surrounding geologic media for long-term containment. Because of the high level of plutonium destruction and degradation achieved by GT-MHR, the isotopic composition of residual plutonium in spent fuel elements would not be practical for use in nuclear weapons and for energy production. Dilution of plutonium within the relatively large volume of GT-MHR fuel elements provides excellent resistance to diversion throughout the fuel cycle. This is accomplished without adversely impacting repository land requirements, since repository loading is determined by decay heat load and not by physical volume. These conditions of safe fuel storage: criticality conditions, conditions of decay heat removing and radiation doses are discussed as well. (author)