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A. I. Leipunskii O. D. Kazachkovskii B. B. Baturov V. V. Stekol'nikov M. A. Barskii Yu. V. Arkhangel'skii V. M. Arkhipov S. M. Blagovolin E. V. Borisyuk I. S. Golovnin V. M. Gryazev M. A. Dem'yanovich A. V. Karpov V. P. Kevrolev B. N. Koverdyaev N. V. Krasnoyarov B. I. Lukasevich V. A. Medvedkov A. M. Smirnov M. F. Troyanov 《Atomic Energy》1971,30(2):196-200
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The steam generator is a very important component of a nuclear power plant. Historically, vertical steam generators came to
be used abroad and horizontal steam generators in our country. Both types of steam generators operate successfully in nuclear
power plants and satisfactorily fulfill their functions, enabling the production of electricity. Repeated attempts to re-examine
the existing concepts in one or another country have been unsuccessful because there are no convincing arguments for this.
Nonetheless, the question of using a different type of steam generator is raised periodically in our country and abroad. This
article briefly reviews different concepts of steam generators. Their parameters, characteristics, and thermal efficiency
are compared and ways to increase the latter are analyzed. It is shown that it is impossible to choose one or the other type
of steam generator without making an exhaustive study and analysis of the layout of the reactor facility and its scheme, servicing,
and operation as part of a nuclear power plant. A comparative analysis of layouts of reactor facilities with different types
of steam generators is made.
Translated from Atomnaya énergiya, Vol. 105, No. 3, pp. 127–135, September, 2008. 相似文献
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B. I. Lukasevich 《Atomic Energy》1979,46(6):487-488
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Yu. G. Dragunov B. I. Lukasevich N. B. Trunov S. A. Kharchenko V. V. Sotskov 《Atomic Energy》2005,99(6):849-857
The basic questions concerning the development of a steam generator for a nuclear power plant with a VVé R-1500 reactor are
presented. The basic design requirements which follow for steam generators from experience in operating analogs at nuclear
power plants and taking account of the requirements for a reactor system are presented. The special features inherent to horizontal-type
steam generators, which have been mastered and are used in nuclear power plants in our country, are noted. The domestic and
world operating experience is taken into account in the development of the design.
It is concluded that the design of the PGV-1500 steam generator satisfies the requirements for the concept of a VVéR reactor
facility for a 1500 MW(e) unit of a nuclear power plant and is competitive on the world market for power-generating equipment
for nuclear power plants.
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Translated from Atomnaya énergiya, Vol. 99, No. 6, pp. 416–425, December, 2005.
An erratum to this article is availabel at . 相似文献
9.
Larionov I. A. Lopatkin A. V. Lukasevich I. B. Moroko V. I. Popov V. E. 《Atomic Energy》2021,129(6):326-330
Atomic Energy - The results of a study of the effect of the homogeneous addition of 237Np, 241Am, 243Am into the fuel on the neutronics characteristics of a lead-cooled fast reactor are reported.... 相似文献
10.
The effect of the internal elements of a tokamak with different coolants on the transmutation rate of long-lived actinides
is studied. The Monte Carlo method is used to calculate nuclear reactions in a homogeneous model of a blanket and in specific
designs of a blanket. The neutron-physical calculations of a homogeneous model of a blanket showed that the absorption of
neutrons by the central column of the tokamak and their moderation by the beryllium coating slow the transmutation rate to
35% of the initial value with the most efficient utilization of lead coolant. For water coolant, this effect is negligible.
In a heterogeneous model of a blanket where water coolant is used, plutonium must be added to the actinides (50%/50%). The
use of lead as the coolant will increase the transmutation rate of the actinides without using plutonium. In this case, it
will be possible to reprocess spent nuclear fuel from more than 10 VVER-1000 in the JUST-T hybrid reactor. 相似文献