[en] On August 21, 1947, the USSR Council of Ministers made a decision on creating Semipalatinsk Nuclear Test Site (STS). The first Nuclear Test on the Test Site was conducted on August 29, 1949, the last one was made on October 19, 1989. In all during 40 years on Semipalatinsk Test Site 116 ground and air and 340 underground nuclear tests were conducted. They brought much damage to health and lives of thousands of people who involuntarily participated in those events. On August 29, 1991, by Kazakstan President's decree STS was closed but the problems of people's rehabilitation, natural landscapes recovering, test-site infrastructure conversion remained. These problems are being solved under direct state programs, intergovernmental agreements of Kazakstan with Russia and the USA, cooperation with different international and foreign organizations, enterprises, scientific-research centers. Kazakstan subsequently constantly pursues the policy of nonproliferation, takes measures on ellimination of nuclear tests consequences and relative infrastructure. The Republic is not involved into military nuclear programs. From its territory all the nuclear weapon was taken away. Kazakstan joined the Agreement on Non-proliferation, signed the Agreement on Safeguards to all Nuclear activity on Kazakh territory with the IAEA

[en] Pulsed graphite reactor IGR was 40 on May 13, 1998. The reactor was constructed to study physical processes occurring in atomic reactors. The IGR creation was initiated by I.V. Kurchatov, the remarkable Soviet physicist and academician. During these years hundreds of atomics units were tested, more than two thousand tests were conducted using IGR reactor. There were also obtained experimental results acknowledged in the world and that will always be of present interest. In relation to this remarkable event, the scientific-technical seminar 'Pulsed Research Reactors'. Application, experimental Researches and results' was held from 9 to 11 of June, 1998

[en] On 14-17 September 1998, in Kurchatov (Kazakstan), II. International Conference on Non-proliferation Problems was held. Representatives from different international organizations (IAEA, UNO, CTBT Organization Preparatory Committee, Austria), from organizations of Kazakstan, Russia, USA, Japan took part in the Conference. At the conference there were 220 participants. Different issues relating to non-proliferation were discussed at the conference sections. The Conference included Plenary Session 'History and Current State of Non-proliferation Problem' and three sections: 1) Practical measures to support non-proliferation regime and Control for Nuclear Tests'; 2) Problems on Eliminating Nuclear tests Consequences and Conversion of Nuclear and Industrial Complex'; 3) Medical and ecological problems of Nuclear Tests Consequences'

[en] The conference was hold in Aktau at the Mangyshlak Power Plant which has the fast neutrons reactor BN-350 and unique facilities for the water desalination. The conference had a great value for cooperation progress in the field of nuclear power engineering taking into account the decision of the Government of Kazakstan to carry out an international tender among largest companies of the world for development of a nuclear power plant projects and its realization in Kazakstan. There were 123 reports. The reports have been presented into following sections: Plenary session; Issues of power engineering and nuclear industry; Perspectives of development; Ecological issues of power engineering; Nuclear power safety. Nuclear technologies; Investigations on thermo-nuclear reactor; Stand reports

[en] In May 14-17, 2000, and on the initiative of the Ministry of Science and High Education of the Republic of Kazakstan with cooperation of Department of Energy US, International Seminar on Nuclear Power Technologies was held in Astana, Kazakhstan. More than 70 reports of scientists from different countries (USA, Russia, Japan and Kazakhstan) were presented during the Seminar. Representatives from different international organizations (European Commission Delegation, IAEA), from organizations of Kazakstan, Russia, USA, Japan took part in the Seminar. In all at the Seminar there were more then 100 participants. The Seminar included Plenary Session, two sections: 1) Nuclear Safety and Nuclear Technologies; 2) Material Investigations for Nuclear and Thermonuclear Power; Workshop: Nuclear Facilities Decommissioning and Decontamination; and Posters

[en] Short communication

[en] Study of structure and content of melting products obtained in set of experiments simulating conditions of severe accident on light water reactor at the stage of interaction of corium melt with water is carried out. It is established, that at contact of 0.7-0.8 kg melt of both the fuel and the constructional materials heated up to 3,700 K with 1.5 kg of cold or hot water the strong fragmentation of melting have being occurred. This process the high-velocity intensive generation of vapour and hydrogen is accompanying. It is shown, that fragmentation rate depends on corium content and height of it discharge into the water

[en] There was investigation of the state of rod-type carbide-graphite fuel elements with a high content of uranium at the mass level of 23-38%) after 70-hour testing in RADA high pressure (20 MPa) nitrogen ampoules of RA reactor. It was discovered that the radiation-chemical stability of the fuel elements in nitrogen greatly depend on the initial state of their structure and uranium content. Comparison of the quantitative factors of chemical and radiation-chemical stability of carbide-graphite fuel elements in nitrogen was made. (author)

[en] The radiation resistance of the (U, Zr)C + C and (U, Zr, Nb)C fuel elements under irradiation in low-flow amplitude reactors under conditions, modeling the operational conditions of such fuel elements by low capacity power regime at nuclear power-motive facility is studied. High efficiency of carbide fuel elements under above-mentioned conditions of reactor testing during approximately 4500 hours is established

[en] Aim of this work is definition of the carbide fuel pins radiation-chemical stability with uranium content at the 15 % (mass) level in the low pressure nitrogen (about 1 MPa) in the condition of irradiation at ∼1000 K in the flow technological channels of the EWG.1 reactor. It is determined, that after 9.5 hour irradiation in the nitrogen flow all fuel pins keep an integrity and an essential portion of the initial strength