Concept, design approaches suited to space nuclear power systems in the range of 20 kWe

A feature of the French preliminary studies of space nuclear power systems of about 20 kwe is the selection of the closed Brayton cycle as the conversion subsystem. As examples of future applications of turbogenerators in space, near or longer term U.S. and Soviet projects are mentioned, including technical advances expected in this field. Several nuclear reactors concepts can be proposed now or in the future. The need for a satisfactory adaptation between the heat source and the converter prompts to further investigate the Brayton cycle capability for that purpose. For instance, a long lifetime thermal spectrum reactor would require a relatively low inlet temperature for moderator thermal conditioning. Cycle configurations featuring one or two separate radiators and possible intercooling are presented. Such arrangements imply a main low temperature radiator made, for instance, of multiple, pivoting tubes. It is shown that the Brayton cycle can offer flexibility and adaptability for a wide range of space missions.

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“…[17]. The present work is a complement and a follow-up of the studies described in the papers [18], [19] and [20].…”

Section: One Of the Main Tasks To Perform As A Consequence Is To Studymentioning

confidence: 76%

“…An example of the application of moderator temperature conditioning using a CBC for a NaK-cooled reactor, can be found in reference [20].…”

Section: Example Of Application To a Direct Cycle Gas-cooled Reactormentioning

confidence: 99%

Flexibility and Adaptability of Closed Brayton Cycles Associated With Low Power Level Space Nuclear Heat Sources

Tilliette

Carré

Proust

1990

Volume 3: Coal, Biomass and Alternative Fuels; Combustion and Fuels; Oil and Gas Applications; Cycle Innovations

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“…Most of the studies performed in recent years on closed cycle gas turbines with a nuclear heat source have been in support of space power systems. In France the focus of Brayton cycle studies has been on multi-kilowatt systems, with evaluations of different reactor types, namely gas-cooled and liquid metal cooled variants (Tilliette, 1989). In the U.S. the potential for future closed Brayton cycle space power systems has been well documented (Harper, 1989).…”

Section: Potential Applicationsmentioning

confidence: 99%

Gas Turbine Power Plant Possibilities With a Nuclear Heat Source: Closed and Open Cycles

McDonald

1990

Volume 3: Coal, Biomass and Alternative Fuels; Combustion and Fuels; Oil and Gas Applications; Cycle Innovations

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With the capability of burning a variety of fossil fuels, giving high thermal efficiency, and operating with low emissions, the gas turbine is becoming a major prime-mover for a wide spectrum of applications. Almost three decades ago two experimental projects were undertaken in which gas turbines were actually operated with heat from nuclear reactors. In retrospect, these systems were ahead of their time in terms of technology readiness, and prospects of the practical coupling of a gas turbine with a nuclear heat source towards the realization of a high efficiency, pollutant free, dry-cooled power plant has remained a long-term goal, which has been periodically studied in the last twenty years. Technology advancements in both high temperature gas-cooled reactors, and gas turbines now make the concept of a nuclear gas turbine plant realizable. Two possible plant concepts are highlighted in this paper, (1) a direct cycle system involving the integration of a closed-cycle helium gas turbine with a modular high temperature gas cooled reactor (MHTGR), and (2) the utilization of a conventional and proven combined cycle gas turbine, again with the MHTGR, but now involving the use of secondary (helium) and tertiary (air) loops. The open cycle system is more equipment intensive and places demanding requirements on the very high temperature heat exchangers, but has the merit of being able to utilize a conventional combined cycle turbo-generator set. In this paper both power plant concepts are put into perspective in terms of categorizing the most suitable applications, highlighting their major features and characteristics, and identifying the technology requirements. The author would like to dedicate this paper to the late Professor Karl Bammert who actively supported deployment of the closed-cycle gas turbine for several decades with a variety of heat sources including fossil, solar, and nuclear systems.

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“…Various reactor concepts presently under consideration include a drain cooled particle bed reactor (4), a HTGR derivative reactor concept and a ZrH moderated particle bed reactor (5,6). A limited experimental program investigating the effect of irradiation on self-supporting structure the mechanical properties of candidate superalloys of the gas cooled reactors (such as various Hastelloys, Haynes 230 and Pyrad 38D) has been initiated in 1987.…”

Section: 3 Htgr Derivative Technologymentioning

confidence: 99%

“…The studies in the area converge on a reactor design with 37 fuel elements (35 mm in diameter) with active core height and diameter of 410 and 340 mm, 100 mm thick axial reflectors of ZrH1.7 and beryllium ( Figure 6 ) ; alternative designs with 19 fuel elements are being further investigated ( 6 ) . In comparison with the drain cooled particle bed reactor, the moderated reactor concept was found to permit a reduction of the fissile fuel inventory by one order of magnitude, but not to significantly reduce the shielding requirement nor the total system mass.…”

Section: Design Studies Of Specific Componentsmentioning

confidence: 99%

Status of the CNES-CEA joint program on space nuclear Brayton systems

Carré¹,

Proust²,

Chaudourne³

et al.

Proceedings of the 24th Intersociety Energy Conversion Engineering Conference

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A cooperative program between the French Centre National d'Etudes Spatiales (CNES) and the Commissariat A 1'Energie Atomique (CEA) was initiated in 1983, to investigate the possible development of 20 to 200 kWe space nuclear power systems to be launched by the next version of the European launcher, Ariane V. After completion in 1986 of preliminary conceptual studies of a reference 200 kWe turboelectric power system, an additional 3 year study phase was decided, with the double objective of assessing the potential advantage of nuclear power systems versus solar photovoltayc or dynamic systans in the 20 kWe power range, and comparing various reactor candidate technologies and system options for 20 kWe space nuclear power systems, likely to meet the projected energy needs of future European space missions. A comprehensive program including conceptual design studies, operating transient analyses and technology base assessment, is currently applied to a few reference concepts of 20 kWe nuclear Brayton and thermoelectric systems, in order to establish sound technical and economical bases for selecting the design options and the development strategy of a first space nuclear power system in Europe.

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Concept, design approaches suited to space nuclear power systems in the range of 20 kWe

Cited by 5 publications

References 1 publication

Flexibility and Adaptability of Closed Brayton Cycles Associated With Low Power Level Space Nuclear Heat Sources

Flexibility and Adaptability of Closed Brayton Cycles Associated With Low Power Level Space Nuclear Heat Sources

Gas Turbine Power Plant Possibilities With a Nuclear Heat Source: Closed and Open Cycles

Status of the CNES-CEA joint program on space nuclear Brayton systems

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