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1.
The basic principles for performing analysis and the systems requirements for large-scale nuclear power in our country are
formulated. The problems of modern nuclear power are examined and ways for modern nuclear power to transition to innovative
development while satisfying these systems requirements for fuel use, handling spent fuel and wastes, and nonproliferation
are indicated. The basic scenario of innovative development in the near term (up to 2030) is based on using predominantly
235U as fuel and water-moderated water-cooled reactors, which have been well mastered, for increasing nuclear capacities with
limited introduction of fast reactors for solving the problem of spent fuel from thermal reactors. In the long term (2030–2050),
a transition to 238U as the primary raw material with fast reactors predominating and complete closure of the nuclear power fuel cycle will be
made.
The journal variant of a report “New-Generation Nuclear Energy Technologies” presented at a meeting of the Scientific and
Technical Council of Rosatom, Moscow, September 27, 2006.
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Translated from Atomnaya énergiya, Vol. 103, No. 3, pp. 147–155, September, 2007. 相似文献
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V. V. Orlov 《Atomic Energy》1994,76(4):336-338
Conclusions The example considered above convinces us of the possibility of developing, without deviating far from experience and traditions,
an economical nuclear technology with a high degree of safety that is capable of forming the foundation for large-scale power
production. This is the obvious path for utilizing the accumulated plutonium without requiring the development of any special
reactors.
Scientific-Research and Design Institute of Energy and Fuels. Translated from Atomnaya énergiya, Vol. 76, No. 4, pp. 345–348,
April, 1994. 相似文献
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F. M. Mitenkov 《Atomic Energy》1996,81(3):611-616
Conclusions Nuclear power has completed the initial stage of development. An efficient international collaboration of scientists and specialists
has been instituted, and this has made it possible to develop and formulate generally accepted requirements and the necessary
conditions for further development. Despite the fact that Russia has a quite powerful scientific and technical potential,
there are no significant reserves in different directions of application of nuclear power, no real plan for the development
of nuclear power in Russia even in the next 15 years. This is apparently explained by the overall state of the economy of
the country.
Journal variant of a report at the Seventh Conference of the Nuclear Society of Russia "New Energy technologies and the role
of nuclear fission and fusion power," October 14–18, 1996, Moscow.
Special Office of Machine Design N. N. Ponomarev-Stepanoi Russian Science Center "Kurchatov Institute". Translated from Atomnaya
énergiya, Vol. 81, No. 3, pp. 163–170, September, 1996. 相似文献
6.
Studies validating rational variants of the development of energy supplies for distributed consumers in the eastern regions of Russia on the basis of the availability of energy resources, transport access, and economic efficiency are indicated in this article. The efficiency and site conditions for the best expansion of a centralized electricity supply, siting of mini thermal and power plants using local fuel, renewable energy sources, low-capacity nuclear power plants, and gas in gas-diesel electricity plants are presented. Proposals are made for developing rational schemes for supplying energy to consumers supplied from the Chaun-Bilibino power system in the Chukotka Autonomous District. 相似文献
7.
P. N. Alekseev V. G. Asmolov A. Yu. Gagarinskii N. E. Kukharkin Yu. M. Semchenkov V. A. Sidorenko S. A. Subbotin V. F. Tsibulskii Ya. I. Shtrombakh 《Atomic Energy》2012,111(4):239-251
Relying on fundamental and applied research performed at the National Research Center Kurchatov Institute, historical experience, and modern mathematical apparatus for systems modeling, experts offer their own view of a strategy for developing nuclear power in Russia. The basic provisions of their strategy for developing nuclear power to 2050, which were developed at the end of 2010 – beginning of 2011, are presented. 相似文献
8.
T. A. Goryachenkova F. I. Pavlotskaya B. F. Myasoedov V. V. Emel'yanov 《Atomic Energy》1992,73(3):747-750
V. I. Vernadskii Institute of Geochemistry and Analytic Chemistry, Russian Academy of Sciences. Translated from Atomnaya Énergiya, Vol. 73, No. 3, pp. 229–233, September, 1992. 相似文献
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V. E. Gmyrko I. I. Grozdov Yu. M. Nikitin A. A. Petrov A. A. Potapov A. F. Finyakin 《Atomic Energy》2007,103(1):518-525
The place and role of channel reactors in nuclear power in our country and the main measures for upgrading and improving the
power generating units of nuclear power plants with RBMK reactors are described. It is shown that the risk indicators for
serious damage to the core of power generating units with RBMK reactors are lower after upgrading and the corresponding IAEA
criterion established for operating nuclear power plants. Upgrading and implementation of a service life extension program
has made it possible to obtain licenses for continuing operation of power generating units with first-generation RBMK reactors
and predicting a service life increase to 45 years. The characteristics of nuclear power plants with channel reactors with
more highly developed internal and natural safety properties are shown in evolutionary designs of the power generating units
MKéR-860,-1000, and-1500, which have protective shells and which meet all requirements for power generating units built today.
It is shown that innovative solutions for the channel reactor concept can be implemented on the basis of the designs of power
generating units with nuclear superheating of steam or on the basis of designs for developing reactors with supercritical
parameters.
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Translated from Atomnaya énergiya,Vol. 103, No. 1, pp. 29–36, July, 2007. 相似文献
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G. L. Lunin V. A. Voznesensky V. G. Fedorov M. F. Rogov V. M. Berkovich I. V. Kukhtevich 《Nuclear Engineering and Design》1997,173(1-3)
Nuclear electricity production in some European countries is based partially or wholly on NPPs with water-cooled water-moderated power reactors (WWERs) of Soviet design. Although only about a quarter of all the WWER units are in operation now in Russia, the country remains responsible, to a certain degree, for supporting the vitality of this well-proven line and its further development. Research work is consecutively carried out and measures are taken in the WWER-based NPPs to improve their safety and cost-effectiveness indices. Nearly constructed WWER-1000/320 units are expected to be commissioned in the Kalinin and Rostov NPPs in the coming years. A new generation of NPPs extensively using passive safety systems are at the final stage of development and are due to be started up after the year 2000. 相似文献
15.
The adoption of the ALARA principle at nuclear power plants in our country is described. Standard dose limits and real dose loads on nuclear power plant personnel are examined. It is shown that the adoption of the ALARA principle is one of the main methods for decreasing the irradiation,, of nuclear power plant personnel. A basic list of measures developed on the basis of the practical implementation of the ALARA principle for decreasing the irradiation of personnel is presented. Translated from Atomnaya énergiya, Vol. 87, No. 5, pp. 335–337, November, 1999. 相似文献
16.
An analysis is made of the role and the place of Russian nuclear power stations on the federal (all-Russia) wholesale market for electrical energy and power, the structure of the costs of producing electricity at these stations, the competitiveness of nuclear energy sources with other producers of electricity. Possible ways are discussed for reducing the cost of producing electricity at nuclear power stations. Journal version of the plenary paper “From the first nuclear power station in the world to the power engineering of the twenty first century” (Annual Conference of Nuclear Society, Obninsk, June 28 to July 2, 1999). Rosénergoatm Concern. Translated from Atomnaya énergiya, Vol. 87, No. 2, pp. 92–101, August, 1999. 相似文献
17.
The prospects for supplying zirconium and hafnium-the main structural and prospective absorbing material for thermal reactors-are
examined in accordance with the strategy for the development of nuclear power in our country up to 2030. The present situation
concerning the use of Russian nuclear fuel is described. The characteristics of the main zirconium alloys used in domestic
and foreign thermal reactors and the approximate requirements for baddeleyite and zirconium concentrates, the distribution
of balance zirconium reserves, and the requirements of the nuclear industry for hafnium metal and hafnium compounds are presented.
Translated from Atomnaya énergiya, Vol. 105, No. 4, pp. 190–194, October, 2008. 相似文献
18.
E. O. Adamov I. Kh. Ganev A. V. Lopatkin V. G. Muratov V. V. Orlov 《Nuclear Engineering and Design》1997,173(1-3)
Under discussion is the management of long-lived high-level wastes in the nuclear energy sector of Russia, the development of which on a large scale in the next century is motivated by the need for arresting the increasing consumption of fossil fuels. The prerequisites for the nuclear power growth consists in the design of naturally safe reactors and development of a transmutational nuclear fuel cycle (NFC) technology. The choice of operations in such a cycle and of their quantitative characteristics, is aimed at minimizing the wastes to approach the radiation balance with the natural uranium extracted and put to use. The paper discusses the way the approximation to the balance between the raw material and waste activity is influenced by introduction of the transmutational NFC (in case 2), inclusion of transmutation reactors into the energy mix (case 1), partial disposal of actinide wastes into outer space, and by recycling of protactinium (case 3). It is shown that such a balance can be sustained for a considerable time in cases 2 and 3 or throughout the operation stage of the future nuclear power (case 1). 相似文献
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