Space nuclear power systems: Yesterday, today, and tomorrow

Акимов, В. Н.; Коротеев, А. А.; Koroteev, A. S.

doi:10.1134/s0040601512130022

Cited by 14 publications

(7 citation statements)

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“…In addition to the United States and Russia, other countries began to study space nuclear power in the 1980s 61 . In 1983, France put forward a conceptual design named the ERATO plan, which aims to design a space nuclear power supply with a service life of 7 years and a power of 20 kW.…”

Section: Application Of Metal Hydride As Moderator Materialsmentioning

confidence: 99%

Advance in and prospect of moderator materials for space nuclear reactors

et al. 2021

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Summary Since 1960s, many countries led by the United States and Russia have done a lot of research on space nuclear reactor power. Moderator is an important functional component in a nuclear reactor operating with a thermal neutron spectrum. This paper reviews the moderation principle, main existing problems, research status as well as main challenges ahead and possible solutions of moderator materials in space nuclear reactor. Aiming at the problems of hydrogen cracking, the low utilization rate of nuclear fuel and hydrogen loss of moderator materials, the assumption of using high entropy alloy hydride as a moderator material is put forward. Moreover, this paper also points out the metal elements suitable for nuclear reactor, while discussing the advantages and disadvantages of several typical elements, hoping to provide a reference for the selection and fabrication of moderator materials. Highlights Sketch the moderating mechanism and the moderator selection principle. Summarize the problems and solutions in the preparation of metal hydride. Summarize the application status of zirconium hydride and yttrium hydride moderator materials. Predict the future development trend and feasible methods of moderator materials.

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Section: Application Of Metal Hydride As Moderator Materialsmentioning

confidence: 99%

Advance in and prospect of moderator materials for space nuclear reactors

et al. 2021

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“…As for megawatt power supply, the nuclear space reactor would be the only option 2 . Numerous nuclear space reactors have been designed, manufactured and even launched over the last six decades 3 . Generally, the nuclear space reactor can be divided into three groups according to the cooling method, including heat pipe‐cooled reactor, 4 liquid metal‐cooled reactor, 5,6 and gas‐cooled reactor 7 …”

Section: Introductionmentioning

confidence: 99%

Thermal‐hydraulic analysis of an open‐grid megawatt gas‐cooled space nuclear reactor core

et al. 2020

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Summary The development of deep space exploration requires space nuclear reactor with higher power and better endurance. In order to meet the increasing high power requirements for space applications, an Open‐grid MEgawatt Gas‐cooled spAce nuclear reactor (OMEGA) is proposed in the paper, which is featured with low specific mass and high energy conversion coefficients. A set of models, including neutron kinetics model, reactivity feedback model and heat transfer model are established. Besides, the space nuclear system analysis code (System Analysis code of MEgawatt gas‐cooled space Reactor [SAMER]) is developed by finite volume method and staggered grid technique for the preliminary safety analysis of the OMEGA conceptual design. Furthermore, the calculation results provided by the SAMER code agree well with the computational fluid dynamics simulation, validating the reliability of the code. Moreover, the transient thermal‐hydraulic responses of the OMEGA under the unprotected reactivity insertion accident (URIA) and the unprotected loss of partial coolant flow accident (LOFA) are obtained and analyzed. The maximum fuel temperature after the URIA has a margin of 262 K from the fuel temperature limit value. The total power after the LOFA is about 68.7% of the rated power, meanwhile, the fuel radial temperature distribution tends to be more uniform with the fuel average temperature unchanged. It can be found that the OMEGA design shows satisfactory safety characteristic and reliability under the URIA and the LOFA scenarios. This paper is the stage summary of the conceptual design work of the OMEGA, and it may provide useful reference for megawatt space nuclear system design and thermal‐hydraulic analysis.

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“…The static energy conversion contains thermoelectric (TE), magnetohydrodynamic (MHD), thermionic, alkali metal thermal‐to‐electric conversion (AMTEC) and thermophotovoltaic. The dynamic conversion includes Brayton, Rankine and Stirling cycle 6 …”

Section: Introductionmentioning

confidence: 99%

Thermal‐hydraulic analysis of gas‐cooled space nuclear reactor power system with closed Brayton cycle

et al. 2020

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Summary Space nuclear reactor power system (SNRPS), especially megawatt power level, is very attractive for the future civil and military space demands. The high‐temperature gas‐cooled reactor coupled with closed Brayton cycle (CBC) can achieve high‐power output for space applications. For the gas‐cooled SNRPS with CBC, dynamic models for all components, including reactor, turbine, compressor, alternator, ducting, pump, recuperator, gas cooler and heat pipe radiator, are developed in this article. Then, a transient system analysis code (SAC‐SPACE) is developed to perform the safety characteristics analysis of the SNRPS. In the full‐power steady‐state analysis, the maximum fuel temperature has a margin of 1323 K from the melting point. Moreover, the transient responses of the SNRPS under the mechanical failure of one Brayton loop (MFOBL1) and the reactivity insertion accident (RIA) are simulated and analyzed. During the MFOBL1, the maximum fuel temperature is 1275 K lower than the melting point, and finally, the reactor power stabilizes at 56.8% of the rated power. For the RIA, as long as the reactivity introduced into the core does not exceed 0.61 $, the SNRPS can reach a new steady‐state safely by itself without other protection strategies. It can be concluded that the SNRPS has good self‐stability due to the negative reactivity feedback of the reactor. This article may provide useful theoretical supports for the design and safety analysis of the gas‐cooled SNRPS with CBC.

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Space nuclear power systems: Yesterday, today, and tomorrow

Cited by 14 publications

References 0 publications

Advance in and prospect of moderator materials for space nuclear reactors

Advance in and prospect of moderator materials for space nuclear reactors

Thermal‐hydraulic analysis of an open‐grid megawatt gas‐cooled space nuclear reactor core

Thermal‐hydraulic analysis of gas‐cooled space nuclear reactor power system with closed Brayton cycle

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