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[en] The main principles of designing emergency protection systems of the VG-400 reactor are briefly considered. Emergency situations referred to the most serious ones are analyzed with account of additional safety system failures or human errors. It is concluded that intensity of eccidents with primary circuit failure lies within the range of 10-7-10-9 per year. This corresponds to the level of accident intensity permitted for NPP with ultimate safety. 3 refs., 3 figs
Source
Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow (Russian Federation). Tsentral'nyj Nauchno-Issledovatel'skij Inst. Informatsii i Tekhniko-Ehkonomicheskikh Issledovanij po Atomnoj Nauke i Tekhnike; Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow (Russian Federation). Inst. Atomnoj Ehnergii; Yadernaya tekhnika i tekhnologiya; (no.3); 80 p; 1990; p. 13-17; TsNIIatominform; Moscow (Russian Federation); ISSN 0321-3099; 
[en] Experimental Design Bureau of Mechanical Engineering (OKBM) specializes in the development of small and medium power reactors having different purposes. They include reactor plants for NPHPP, nuclear district heating power plants and propulsion plants. Small and medium power plants have simpler processes of electricity and heat production, less systems, simpler control algorithms and considerably enhanced inherent safety properties. These plants are mainly equipped with passive safety systems. These properties are especially characteristic for reactor plants of nuclear district heating power plants and HTG reactor plants. The designs of small and medium power plants actually provide a high degree of control automation which considerably reduces workload on the personnel in both normal and abnormal operation conditions. All this allows the reduction in personnel for small and medium power reactors if compared to high capacity reactor plants. But due to objective reasons the specific number of personnel (man/MW) for average and especially small capacity reactors considerably exceeds the value for high capacity reactor plants. At the same time one can propose a set of organization - technical measures allowing the increase in this value in future. Safety requirements imposed for small and average capacity reactors are the same or more strict than those for high capacity reactors. That's why the requirements to the training of personnel for such reactor plants are not allowed to be lowered if compared to the requirements imposed to the personnel of high capacity reactors. (author)
Source
International Atomic Energy Agency, Vienna (Austria); 129 p; ISSN 1011-4289; ; Jan 2001; p. 89-94; 2 refs, 5 tabs
; Jan 2001; p. 89-94; 2 refs, 5 tabs
[en] The history of development of heavy-water reactor engineering in Russia is considered. The technological schemes of the first russian heavy-water reactors OK-180, OK-190, OK-177 and L-2 are presented. The long-standing experience of the operation of these reactors gives evidence of their wide potentials for isotope production. The concept of the new heavy-water reactor is discussed. On particular, the project of the sub-critical accelerator driven system based on the heavy-water blanket and the proton accelerator is developed for the neutron generator
[ru]
Рассмотрена история развития тяжеловодного направления реакторостроения в России. Представлены технологические схемы тяжеловодных реакторов ОК-180, ОК-190, Л-2 и ОК-177. Многолетний опыт экпслуатации тяжеловодных реакторов свидетельствует об их широких возможностях использования в качестве наработчиков изотопной продукции. Обсуждается конценция нового тяжеловодного реактора. В частности, рассматривается проект электроядерного генератора нейтронов на основе тяжеловодного бланкета и ускорителя протоновSource
Litovkina, L.P.; Titarenko, Yu.E. (comps.); Institute Teoreticheskoj i Ehksperimental'noj Fiziki, Moscow (Russian Federation); 275 p; ISBN 5-85165-662-X; ; 1999; p. 72-81; International conference on sub-critical accelerator driven systems; Moscow (Russian Federation); 11-15 Oct 1999; 2 refs., 5 figs.
; 1999; p. 72-81; International conference on sub-critical accelerator driven systems; Moscow (Russian Federation); 11-15 Oct 1999; 2 refs., 5 figs.
No abstract available
Source
Ministerstvo Rossijskoj Federatsii po Atomnoj Ehnergii, Moscow (Russian Federation); Yadernoe Obshchestvo Rossii, Moscow (Russian Federation); Gosudarstvennyj Nauchnyj Tsentr Rossijskoj Federatsii Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov, Dimitrovgrad (Russian Federation); 104 p; ISBN 5-85165-655-7; ; 2001; p. 273; 12. Annual conference of the Nuclear Society of Russia. Research reactors: science and high technologies; 12. Ezhegodnaya konferentsiya Yadernogo Obshchestva Rossii. Issledovatel'skie reaktory: nauka i vysokie tekhnologii; Dimitrovgrad (Russian Federation); 25-29 Jun 2001
; 2001; p. 273; 12. Annual conference of the Nuclear Society of Russia. Research reactors: science and high technologies; 12. Ezhegodnaya konferentsiya Yadernogo Obshchestva Rossii. Issledovatel'skie reaktory: nauka i vysokie tekhnologii; Dimitrovgrad (Russian Federation); 25-29 Jun 2001
[en] Designs of the GT-MGR and the MGR-T modular high-temperature gas-cooled reactors (HTGCR) are based on the international experience to design and to operate HTGCR with a prismatic fuel assemblies and ceramic minute particles, as well as, on the innovation approaches as applied to the energy conversion system. The operation safety of the modular high-temperature gas-cooled reactor NPP is ensured by development of the inherent safety and by use of the passive safeguards. Paper describes approaches to analyze safety, the applied codes and their verification. One dwells upon the results of analysis of the most severe accidents and of the the accident consequences
[ru]
Проекты модульных высокотемпературных газоохлаждаемых реакторов (ВТГР) ГТ-МГР и МГР-Т базируются на мировом опыте разработки и эксплуатации ВТГР с призматическими ТВС и керамическим микротопливом, а также на инновационных решениях по системе преобразования энергии. Высокий уровень безопасности АЭС с модульными ВТГР достигается путем развития свойств внутренней самозащищенности и использования пассивных систем безопасности. Представлены подходы к анализу безопасности, используемые коды, их верификация. Рассмотрены результаты анализа наиболее тяжелых с точки зрения повреждения активной зоны и радиационных последствий аварийJournal
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