Submersion-Subcritical Safe Space (S4) reactor

King, Jeffrey C.; El‐Genk, Mohamed S.

doi:10.1016/j.nucengdes.2005.12.010

Cited by 50 publications

(7 citation statements)

References 13 publications

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“…In 2007, King and El-Genk proposed the design of a novel Submersion Subcritical Safe Space Reactor (S4) [6,7]. The S4 reactor has a system power of 100 kWe and is based on the design of a Heat Pipe Segmented Thermo-Electric Module Cascade (HP-STMC) and an Alkali Metal Thermal-to-Electric Converter (AMTEC) integrated space reactor power system.…”

Section: [Insert Figure 4 Here]mentioning

confidence: 99%

“…In 2007, King and El-Genk [6,7] designed the Submersion Subcritical Safe Space Reactor (S4) to enhance the safety of space missions and ensure the safety of reactors and space systems in the event of launch abort accidents or operational failures. The S4 reactor was based on a segmented thermoelectric pile (HP-STMC) and an Alkali Metal Thermal-to-Electric Converter (AMTEC) integrated space reactor power system.…”

Section: Introductionmentioning

confidence: 99%

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Research and development of helium-xenon Brayton cycle technology: A review

Chen,

Song,

Qian

et al. 2024

NSO

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Section: [Insert Figure 4 Here]mentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Research and development of helium-xenon Brayton cycle technology: A review

Chen,

Song,

Qian

et al. 2024

NSO

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“…water immersion). Rhenium has been used in various conceptual reactor designs as a spectral shift absorber to offset reactivity increases that can result from water submersion in postulated accident scenarios [King and El-Genk, 2006;Poston, 2002;Tournier, 2004a, 2004b;Truscello and Rutger 1992]. At present no decision has been made regarding inclusion of rhenium in the FSP reactor design.…”

Section: Data Sets Included In Table 4 Additional Related Experimentsmentioning

confidence: 99%

Reactor Testing and Qualification: Prioritized High-level Criticality Testing Needs

Bragg‐Sitton¹,

Bess²,

Werner³

et al. 2011

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“…It can be found that the specific mass is relevant with core outlet temperature, thermal‐to‐electric conversion options, and coolant types. The three lowest specific mass belong to TEM, 11 S 4 , 12 and JIMO, 13 which are gas‐cooled reactors combined with dynamic thermal‐to‐electric conversion system. They have higher heat transfer coefficients, 14 including thermal‐to‐electric conversion coefficient and waste heat dissipation coefficient.…”

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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Submersion-Subcritical Safe Space (S4) reactor

Cited by 50 publications

References 13 publications

Research and development of helium-xenon Brayton cycle technology: A review

Research and development of helium-xenon Brayton cycle technology: A review

Reactor Testing and Qualification: Prioritized High-level Criticality Testing Needs

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

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