2016
DOI: 10.1002/er.3633
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A concept design of supercritical CO2cooled SMR operating at isolated microgrid region

Abstract: Summary Most of the small modular reactor (SMR) concepts developed in the past have compact size and a longer life reactor core than the conventional nuclear power plants. However, these concepts have not achieved the full modularization including power conversion system. This study suggests an innovative concept of a reactor cooled by supercritical state carbon dioxide (S‐CO2). A reactor core with uranium carbide fuel controlled by drum type control rods was designed. The core has long life (20 years) without… Show more

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Cited by 37 publications
(12 citation statements)
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“…Schematic figure of Korea Advanced Institute of Science and Technology Micro Modular Reactor (KAIST‐MMR)…”
Section: Kaist Micro Modular Reactormentioning
confidence: 99%
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“…Schematic figure of Korea Advanced Institute of Science and Technology Micro Modular Reactor (KAIST‐MMR)…”
Section: Kaist Micro Modular Reactormentioning
confidence: 99%
“…KAIST-MMR is a conceptual small modular nuclear power plant that integrated with S-CO 2 -cooled fast reactor core and S-CO 2 simple recuperated power conversion system together. 28 To enhance the existing advantages of SMR such as low construction cost and easy site selection, the whole size of the KAIST-MMR is selected to be transportable by land or maritime transportation. The compact size of KAIST-MMR can be achieved by eliminating the IHX between the reactor core and the power conversion cycle.…”
Section: Kaist Micro Modular Reactormentioning
confidence: 99%
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“…Although some concept designs of the nuclear power generation systems utilized the S‐CO 2 power cycle, there are few studies on the coupling system of the pool‐type liquid metal cooled fast reactor and the S‐CO 2 cycle. Moisseytsev and Sienicki compared different layouts for the S‐CO 2 cycle coupled to the sodium‐cooled fast reactor.…”
Section: Introductionmentioning
confidence: 99%
“…16,17 To further improve the cycle performance, the following investigations were conducted by the researchers: (a) comparing cycle layouts, such as the recompression cycle, the intercooling cycle, and the precompression cycle 10,18 ; (b) adopting the combined cycle and increase the bottom cycle, such as the Rankine cycle and the transcritical CO 2 cycle 19,20 ; (c) adding other gases to S-CO 2 to improve the physical properties of the working fluids 21 ; (d) reheating the working fluid to increase the turbine power. 10,22,23 Although some concept designs of the nuclear power generation systems utilized the S-CO 2 power cycle, [24][25][26] there are few studies on the coupling system of the pool-type liquid metal cooled fast reactor and the S-CO 2 cycle. Moisseytsev and Sienicki 22 compared different layouts for the S-CO 2 cycle coupled to the sodium-cooled fast reactor.…”
Section: Introductionmentioning
confidence: 99%