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Advanced Space Nuclear Reactors

A special issue of Energies (ISSN 1996-1073). This special issue belongs to the section "B4: Nuclear Energy".

Deadline for manuscript submissions: closed (30 November 2023) | Viewed by 936

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Guest Editor
Georgia Institute of Technology, G. W. Woodruff School of Mechanical Engineering, Nuclear and Rediological Engineering Program, North Ave NW, Atlanta, GA 30332, USA
Interests: reactor phycics; fuel cycles; reactor engineering; multiphysics
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Special Issue Information

Dear Colleagues,

During the last few years, we have seen a strong push towards developing base power sources for nuclear applications in space as well as nuclear engines to support space transits. For example, fission surface power is robust and reliable regardless of the deployed environment, such as the Moon or Mars. An additional example is nuclear propulsion technology, which has the potential for future crewed missions to Mars. This technology is expected to enable reduced interplanetary travel times, which could increase the crew's safety by reducing exposure to cosmic radiation and other hazards of deep space travel. There are ongoing activities by NASA and the Defense Advanced Research Projects Agency (DARPA), who are assisted by multiple industry partners and national labs, to demonstrate this technology in the next decade.

This Special Issue of Energies on “Advanced Space Nuclear Reactors” is focused on existing and novel designs related to the advancement of nuclear reactor applications in space. The focus is on the designs, applications, and methodologies to support the deployment of these advanced systems.

Topics include, but are not limited to, the following research topics:

  • Fission surface power;
  • Nuclear thermal propulsion;
  • Nuclear electric propulsion;
  • Demonstration Rocket for Agile Cislunar Operations;
  • Advancements in radioisotope thermoelectric generator;
  • Computational tools to support the development and licensing of nuclear space systems.

Manuscripts addressing combinations of computational tools with design challenges are also welcome.

Dr. Dan Kotlyar
Guest Editor

Manuscript Submission Information

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Keywords

  • space nuclear
  • nuclear propulsion (NTP and NEP)
  • radioisotope thermoelectric generator (RTG)
  • fission surface power.

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Published Papers (1 paper)

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Research

22 pages, 7090 KiB  
Article
Analysis of the Radiator Loss Safety Boundary of a Space Reactor Gas Turbine Cycle with Multiple PCU Modules
by Wenkui Ma, Ping Ye, Yue Gao, Yadong Hao, Yi Yao and Xiaoyong Yang
Energies 2024, 17(3), 597; https://doi.org/10.3390/en17030597 - 26 Jan 2024
Cited by 1 | Viewed by 619
Abstract
The development of space exploration technologies puts higher demand on space power systems. The space reactor gas turbine cycle (SRGTC) has the advantages of compact configuration and small mass and volume and is one of the optimal options for future high-power space power [...] Read more.
The development of space exploration technologies puts higher demand on space power systems. The space reactor gas turbine cycle (SRGTC) has the advantages of compact configuration and small mass and volume and is one of the optimal options for future high-power space power systems. The SRGTC operates in an isolated island state and the radiator is fragile if it is hit by asteroids and space debris. The transient characteristics of the SRGTC are fundamental for safe operation in radiator loss accidents. In this paper, a dynamic model for the SRGTC is established, and the performance of the SRGTC with dual power conversion unit (PCU) modules (SRGTC-DPCU) after radiator loss was investigated. The results indicated that the waste heat of the system was accumulated in the radiator after radiator loss, which increased the consumed power of the compressor and further led to speed fluctuations. The bypass valve control and the temperature negative feedback effect can ensure the safe operation of the shaft and the reactor. More radiator loss decreased the speed far below the rated speed and exceeded the safety margin of the bypass valve control, which further led to system shutdown. There is a safety boundary of radiator loss accidents. Furthermore, the coupling effects of multiple PCUs after radiator loss were analyzed. The working fluid inventory was redistributed among the PCU modules. The reduction of working fluid inventory in the accident PCU module promoted the safety boundary. This study provides a reference for the operation of the SRGTC. Full article
(This article belongs to the Special Issue Advanced Space Nuclear Reactors)
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