[en] Russian Fusion Materials Program (1998-2000, Minatom of Russia) includes the radiation-resistance low (reduced) activation vanadium-titanium-chromium alloys, ferritic-martensitic steels and beryllium as the key to the realization of fusion reactors. The focus is the Russian project DEMO reactor, DEMO test modules, ITER and fusion relevant intense neutron sources. The Program include industrial technology and production/fabrication, heat treatment, mechanical properties, microstructure and baseline properties characterization, development of weld/joint procedures, corrosion/compatibility studies, evaluation of irradiation effects on properties, activation and transmutations properties and certification of the suggested materials

[en] NTSC was created in November, 1997 as an association of experts in all the areas of nuclear and radiation safety and radioactive materials handling The main goal of creation is investigation of safety aspects of nuclear power in the Republic of Kazakhstan, taking into account the interests of environment and human health protection in the regions of nuclear industry units allocation. The Center was created with support and special cooperation with the US, has grown and developed cooperative ties with several other countries.In the report are enumerate the main directions of NTSC activity, general directions of cooperation, current and completed activity, planing activity

[en] To enhance the efficiency of nuclear materials control and accounting a complex of weight sensors and a complex of 'smart shelves' were put into operation at one of the facilities of the RSC 'Kurchatovskiy Institute'. The weight sensors and 'smart shelves' equipment designed in ORNL provide for a continuous, remote measuring of weight of the controlled items and their constant inventory valuation. After inspection, testing, adjustment and finishing of the used software the both complexes were built up at one of the nuclear material depositories. The complexes control more than 20 kg of uranium-containing nuclear material with enrichment of 90% by U-235, in form of small non-identified components placed in specific casks. Application of the weight sensor complex, combined with the complex of 'smart shelves', provides for on-line detection of the clandestine, long-term removal of nuclear material in small portions

[en] On the territory of Kazakstan there has been accumulated a large amount of radioactive waste (RW) dangerous for environment and people's health as a result of the development of metal mining and uranium production industries, atomic power engineering and 40 year long nuclear peaceful and military tests. Systematic study of RW quantitative and qualitative characteristics on Kazakstan territory began in 1993 and it relates to creation of RK National Nuclear Center and RK Atomic Energy Agency. At 'Baikal-1' stand complex of the Institute of Atomic Energy in January 1995 there was put into operation the first section of technological complex on receiving and storing of ampoule sources of ionizing radiation (ASIR). Their total quantity that operates at Kazakstan organizations and enterprises exceeds 80000 pieces. 20000 pieces of them are subject to burial

[en] As tests on creep of the austenitic steel 03Cr20Ni45Mo4NbBZr on 873-973 K temperature interval showed some anomalies took place on creep curves, when before a non-steady stage of creep there was a section, on which the sample deformation didn't increase, but for some cases decreased with time. For instance, under neutron irradiation at temperature of 873 K and tensions of 296 or 302 MPa the sample deformation was not observed for initial 10 h. After this period of time the creep curves behaved as standard type ones and respectively for 400 h and 810 h became conventional. Decreasing of tension down to 178 MPa resulted in the section of non-changed in value strain reached 230 h. At equal temperature and tension rising of neutron flux density leaded to more clear appearance of the negative creep. The phenomenon of the negative creep was further investigated on non-irradiated aluminium alloy D16

[en] The problem of ⁹³ Zr accumulation and its transmutation is addressed. It is shown that neutron flux required for ⁹³ Zr transmutation is unachievable in fission reactor. Therefore transmutation of ⁹³ Zr in the fusion based facility is proposed. It is demonstrated that current ITER fusion reactor project can be sufficiently served as a transmuter to resolve the problem of ⁹³ Zr accumulation within the time period of several decades

[en] Even though not all the world's nations have developed a nuclear power industry, nuclear safety is unquestionably an international issue. Perhaps the most compelling proof is the 1986 accident at Chornobyl nuclear power plant in what is now Ukraine. The U.S. Department of Energy conducts a comprehensive, cooperative effort to reduce risks at Soviet-designed nuclear power plants. In the host countries : Armenia, Ukraine, Russia, Bulgaria, the Czech Republic, Hungary, Lithuania, Slovakia, and Kazakhstan joint projects are correcting major safety deficiencies and establishing nuclear safety infrastructures that will be self-sustaining.The U.S. effort has six primary goals: 1. Operational Safety - Implement the basic elements of operational safety consistent with internationally accepted practices. 2. Training - Improve operator training to internationally accepted standards. 3. Safety Maintenance - Help establish technically effective maintenance programs that can ensure the reliability of safety-related equipment. 4. Safety Systems - Implement safety system improvements consistent with remaining plant lifetimes. 5. Safety Evaluations - Transfer the capability to conduct in-depth plant safety evaluations using internationally accepted methods. 6. Legal and Regulatory Capabilities - Facilitate host-country implementation of necessary laws and regulatory policies consistent with their international treaty obligations governing the safe use of nuclear power

No abstract available

[en] BN-350 is the first in the world fast power reactor. A large series of neutron physical experiments was fulfilled during its operation (i.e. beginning from 1973). Part of these experiments was done for providing the reliable and safe exploitation of the BN-350 reactor itself. But the most part of complicated experiments was fundamental in nature and its results have intransigent importance.The experimental data obtained on the BN-350 reactor by using a number of independent experimental methods (gravichemistry, radiometry, mass-spectroscopy, activation etc.) after corresponding preparation could present very reliable and full basis for validation of calculations of uranium and plutonium nuclide composition change during the reactor operation and also the calculations of physical parameters of reactor taking into account mutual influence of neutron and nuclide fields. In this connection it is proposed to carry out the international project on keeping the unique data obtained in the BN-350 reactor. The goal of the project is reducing the results of the neutron-physical experiments being carried out on the BN-350 reactor during all years of it's operation to the form available for making use of it by the world scientific community for verification of the neutron calculation methods and corresponding program complexes, nuclear constants libraries. Thus, the accomplished experience will be saved

[en] Modular helium reactor with the gas turbine (GT-MHR) is a perspective power reactor plant for the next century. The project reactor is based on experience of operation more than 50 gas-cooled reactors on carbon dioxide and helium, and also on subsequent achievements in the field of realization direct gas turbine Brayton cycle. To the beginning of 90 years, achievements in technology of gas turbines, highly effective recuperators and magnetic bearings made it possible to start development of the reactor plant project combining a safe modular gas cooled reactor and a power conversion system, realizing the highly effective Brayton cycle. The conceptual project of the commercial GT-MHR reactor plant fulfilled in 1997 by joint efforts of international firms, combines a safe modular reactor with an annular active core of prismatic fuel blocks and a power conversion system with direct gas turbine cycle. The efficiency of GT-MHR gas turbine cycle at level of about 48% makes it competitive in the electricity production market in comparison with any fossil or nuclear power stations