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Experience in starting and tuning (adjusting) operations with the BN-350 reactor and in its initial power production
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The BFS-1 complex: A microtron for studying fast-reactor neutron spectra
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Design and operating experience with fast reactors in the USSR
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Fourth International Conference of the United Nations on the Peaceful Use of Atomic Energy Prospects of the Development of Nuclear Power in the USSR
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Efficient utilization of fuel in fast power reactors
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Improvement of physical characteristics of fast plutonium reactors by using U233 and thorium
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Experience in the building and startup of the BOR-60 reactor
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Development of nuclear power with fast-neutron reactors in the USSR
In considering the prospects of nuclear power development, we must not exclude the possibility of new solutions. However, experience and estimates show that the way which we have chosen will lead to the soluti...
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A nuclear power station with the BN-600 reactor
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Operating experience with the BR-5 reactor over the 1959–1966 period
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Construction of an atomic electric power plant based on the BN-350 reactor
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Sodium technology and equipment of the BN-350 reactor
Information relating to the installation of a dual-purpose atomic station with a BN-350 reactor on the Mangyshlak peninsula in the USSR was presented in contributions to the Third International Conference on t...
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The BN-350 and the BOR fast reactors
The reloading system and the construction of the safety control mechanisms of the BN-350 reactor are described and problems of emergency cooling andtransient processes are discussed. The experimental BOR assem...
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Use of nonuranium diluents for plutonium in large fast breeder reactors
The authors study the physical characteristics of fast breeder reactors with cylindrical and ringshaped cores, and also the characteristics of infinite lattices of heterogeneously-arranged large fuel cassettes...
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Feasibility of using thorium in fast power reactors
This paper gives data on the feasibility of using U233 and thorium in a breeding-reactor system. From the viewpoint of doubling time, the most promising method is the simultaneous use of U233-Th and Pu239−U238 in...
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Sodium-cooled fast reactors
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Investigation of the BR-5 fast reactor (space-energy neutron distributions)
The present article provides a brief description of a fast reactor which is in operation and of its basic experimental equipment. The reactor is designed for studying various materials and for technological an...
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The future of fast reactors
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A fast-neutron pulse reactor
In June, 1960, criticality was reached on the fast-neutron pulse reactor constructed at the United Institute of Nuclear Studies.
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Studies in the physics of fast neutron reactors