Work on nuclear power plants for space

Conclusions It should be noted that the space problems gave an unprecedented impetus to improving computational methods and design of reactors and shielding and the development of the latest technology. This is not surprising, since the designs required that the mass of the nuclear power plant be determined to within several kilograms. The placement of every kilogram of a satellite in orbit costs several thousands of dollars. The development of nuclear rocket motors and the first thermionic systems "Topaz" in the world was a very important achievement in space nuclear technology. Unfortunately, as sometimes happens in practice, this achievement was far ahead of its time and remains unused. Translated from Atomnaya énergiya, Vol. 80, No. 5, pp. 357–361, May, 1996.     

High-temperature heat pipes for power modules of space nuclear power systems

The results of an experimental analysis of the technology for producing high-temperature heat pipes and choosing their structure so as to ensure a long service life and high performance characteristics required for the power modules of space nuclear power systems with an out-of-core energy conversion system are examined. It is estimated that the operation of molybdenum-lithium heat pipes, fabricated using the technology developed, for the power modules of such nuclear power systems will be stable for >10⁵ h. 2 figures, 1 table, 13 references. State Enterprise Krasnaya Zvezda. Translated from Atomnaya énergiya, Vol. 89, No. 1, pp. 82–86, July, 2000.     

A concept of radiation safety for nuclear power units in space and its implementation in the “Kosmos-1900” satellite

Conclusion Experience in ensuring radiation safety for nuclear units in outer space has shown the adequacy of using two independent systems: a booster system and a system for dispersing the reactor based on using active means to break up its structure.The theoretical calculations and experimental research performed in the Soviet Union, the engineering and construction development, and testing have confirmed the effectiveness of the booster and reactor dispersion systems as well as their capability to operate with the necessary reliability during normal operating conditions and in accident situations aboard space equipment.This article is a variant of a report presented at the Sixth Symposium on Nuclear Power in Outer Space (Albuquerque, January 1989).Translated from Atomnaya Énergiya, Vol. 66, No. 6, pp. 380–383, June, 1989.     

Concept of nuclear safety and radiation safety of thermionic nuclear power units for spacecraft

Translated from Atomnaya Énergiya, Vol. 69, No. 5, pp. 267–271, November, 1990.     

Open-cycle multi-megawatt MHD space nuclear power facility

The results of calculations of the characteristics and development of a scheme and technical make-up of an open-cycle space power facility based on a high-temperature nuclear reactor for a nuclear rocket motor and a 20 MW Faraday MHD generator are presented. A heterogeneous channel-vessel IVG-1 reactor, which heated hydrogen to 3100 K, with the pressure at the exit from the reactor core up to 5 MPa, burn rate 5 kg/sec, and thermal power up to 220 MW is examined. The main parameters of the MHD generator are determined: Cs seed fraction 20%, stopping pressure at the entrance 2 MPa, electric conductivity ≈ 30 S/m, Mach number ≈ 0.7, magnetic induction 6 T, electric power 20 MW, specific energy extraction ∼4 MJ/kg. The construction of the scheme of a MHD facility with zero-moment exhaust of the working body and its main characteristics are presented. Translated from Atomnaya énergiya, Vol. 105, No. 3, pp. 135–144, September, 2008.     

Service life extension of power-generating units in nuclear power plants

Questions arising in the analysis of service life extension of power-generating units in nuclear power plants under the conditions of national realities are analyzed. Science and Technology Center for Nuclear Reactor Safety. Translated from Atomnaya énergiya, Vol. 88, No. 1, pp. 14–21, January, 2000.     

Efficiency of producing additional power in units of nuclear power stations containing water-cooled-water-moderated reactors

Conclusions There is a basic possibility to raise the maximum power of a unit containing the VVÉR-1000 reactor in the course of the fuel charge burn-up and with lowering the coefficient of the energy-release nonuniformity in the reactor core. It is more advantageous economically to obtain additional power in carrying the peak load. With the duration of such operating conditions for 1000–2000 h/yr savings can amounts to 1–4 million rubles per year per 100 MW of additional power when compared to peaking GTP.It is necessary to analyze in more detail the safety as well as technical and economic indexes of the VVÉR-1000 and of the entire power unit both under normal operating conditions and in emergency situation for the proposed elevated power mode.It is necessary to develop a procedure of experimental substantiation of a possible forcing level for the operating units of the NPS containing a VVÉR. The interested agencies should be involved in this development. Technical and economic advisability of making up a set of power-unit equipment suitable to carry short load peaks and prolonged elevation of the electric loads in the EPS should be determined on this basis and changes and additions should be introduced when developing new designs.Translated from Atomnaya Énergiya, Vol. 61, No. 6, pp. 397–401, December, 1986.     

Prospects for the use of thermionic nuclear power plants for interorbital transfers of space vehicles in near space

Scientific-Production Association "Krasnaya Zvezda." Translated from Atomnaya Énergiya, Vol. 73, No. 5, pp. 346–350, November, 1992.     

Prospects of using thermoelectric nuclear power generators for manufacturing of materials in space

State Enterprises Krasnaya Zvezda. Nuclear Reactor Institute of Kurchatov Institute Scientific Center. Translated from Atomnaya Énergiya, Vol. 75, No. 4, pp. 254-259, October, 1993.     

Choice of parameters for current conversion systems in high-power space nuclear power systems

The energy-mass and operational characteristics of a nuclear electrorocket propulsion system based on thermionic reactor-converters largely depend on the parameters of the current converter and the onboard cable network. The decrease of the specific mass of a nuclear electrorocket propulsion system due to the choice of the temperature regime of the current converter and the onboard cable network as well as the frequency of the supply voltage is examined. Investigations have shown that increasing the working temperature of the onboard cable network and current converter makes it possible to decrease the specific mass of the nuclear electrorocket propulsion system by 33–83%, as a result of which the useful load fraction of the spacecraft increases from tens of percent to a factor of 2–3, 1 figure, 6 references. Translated from Atomnaya énergiya, Vol. 89, No. 1, pp. 78–81, July, 2000.     

Reactor units developed by OKBM Afrikantov for low- and medium-capacity nuclear power plants

A system of requirements for low- and medium-capacity nuclear power-generating units with guaranteed market demand is presented. OKBM Afrikantov has developed designs for reactor units for low- and medium-capacity nuclear power plants that can be used as power sources in floating nuclear power plants for supplying heat and power in remote regions in the coastal zone, power-generating units as components of nuclear water desalination complexes and for supplying power for marine oil drilling platforms, stationary nuclear power plants for supplying heat and power in separate regions, large industrial enterprises, and cities. ABV, KLT, RITM, VBER, and HTGR reactor units for power sources of this type are reviewed and their characteristic features as well as those of nuclear power plants based on them are indicated.     

热管空间核反应堆电源的研究进展

随着人类对宇宙太空的深入探索,对于提供能量的电源要求也在逐步提高,空间核反应堆电源在执行深空探测任务中脱颖而出。热管核反应堆由于具备非能动性、寿期长、可靠性高等优势,成为目前空间核反应堆领域的研究热点。本文通过重点介绍典型热管堆的概念设计系统以及在Kilopower中的应用,对热管电源系统(Heatpipe Power System,HPS)、由热管控制的火星探索反应堆(The Heatpipe-operated Mars Exploration Reactor,HOMER)、安全可负担裂变引擎方案(Safe Affordable Fission Engine,SAFE)以及Kilopower进行了重点调研,归纳总结了各个反应堆的结构设计、燃料选择、热管排布、功率设计等,以期对未来热管空间核反应堆电源的设计研究提供思路和参考。     

Composition and structure of simulation models for evaluating decommissioning costs for nuclear power plant units

The methodological and practical approaches to realizing an iterative multiple-criterion analysis for evaluating the decommissioning costs of the power-generating units of nuclear power plants and the optimal structure of the analysis using information technologies are examined. The objective prerequisites which have been established and facilitate the development and use of decommissioning simulation models in practical work are analyzed.     

VBÉR-300 reactor system and power-generating units for regional nuclear power production

The basic design solutions and characteristics of the VBéR-300 reactor system for the power-generating units of 150–300 MW(e) nuclear power plants and regional nuclear heat-and-electricity plants are described. The reactor system implemented as a unit is based on the technologies and solutions used for marine nuclear power systems, which have been corroborated by experience in operating nuclear-powered icebreakers. The technical-economic advantages of floating power-generating units are substantiated. __________ Translated from Atomnaya énergiya, Vol. 102, No. 1, pp. 35–39, January, 2007.