Nuclear Engineering and Technology

  • 제54권3호
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  • Pages.877-887
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  • 2022
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Design of a direct-cycle supercritical CO2 nuclear reactor with heavy water moderation

  • 투고 : 2021.07.19
  • 심사 : 2021.09.26
  • 발행 : 2022.03.25
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초록

A new reactor concept is described that directly couples a supercritical CO2 (sCO2) power cycle with a CO2-cooled, heavy water moderated pressure tube core. This configuration attains the simplification and economic potential of past direct-cycle sCO2 concepts, while also providing safety and power density benefits by using the moderator as a heat sink for decay heat removal. A 200 MWe design is described that heavily leverages existing commercial nuclear technologies, including reactor and moderator systems from Canadian CANDU reactors and fuels and materials from UK Advanced Gas-cooled Reactors (AGRs). Descriptions are provided of the power cycle, nuclear island systems, reactor core, and safety systems, and the results of safety analyses are shown illustrating the ability of the design to withstand large-break loss of coolant accidents. The resulting design attains high efficiency while employing considerably fewer systems than current light water reactors and advanced reactor technologies, illustrating its economic promise. Prospects for the design are discussed, including the ability to demonstrate its technologies in a small (~20 MWe) initial system, and avenues for further improvement of the design using advanced technologies.

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과제정보

The authors are grateful to their colleagues for their numerous technical contributions, including Greg Markham (leak-before-break assessment), Sam Miller (heat transfer modeling), Olu Omotowa (safety event identification), and Michael Pierson (plant layout). We are also grateful to Tim Held, Jason Miller, and David Buckmaster at Echogen Power Systems for their contributions to sCO2 cycle design and analysis.

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