DEVELOPMENT OF A SUPERCRITICAL CO<sub>2</sub>BRAYTON ENERGY CONVERSION SYSTEM COUPLED WITH A SODIUM COOLED FAST REACTOR

Cha, Jae-Eun; Lee, Tae‐Ho; Eoh, Jaehyuk; Seong, Sung-Hwan; Kim, Seong-O; Kim, Dong-Eok; Kim, Moo-Hwan; Kim, Tae Woo; Suh, Kyun-Yul

doi:10.5516/net.2009.41.8.1025

Cited by 67 publications

(11 citation statements)

References 2 publications

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“…Summing up (8) and (9), the total torque of the compressor is obtained: Therefore, through (5), (6), and (10), the enthalpy increase, pressure increase of fluid through the compressor, and total torque of the compressor can be obtained.…”

Section: Basic Model Of Compressormentioning

confidence: 99%

“…Another option to apply S-CO 2 Brayton cycle working as the power conversion system of existing Gen IV reactor concept, which tries to take advantages of large amount of R&D work of these new concepts and improve the cycle efficiency at the same time. Feasibility of S-CO 2 Brayton coupled to sodium fast reactor concept KALIMER-600 [8], lead fast reactor concept STAR-LM [9], and SSTAR [10]. S-CO 2 Brayton cycle configuration, as well as the transient performance and control strategy of these concepts, has been carried out, which shows great potential for applying S-CO 2 Brayton cycle on these new reactor concepts.…”

Section: Introductionmentioning

confidence: 99%

“…Different transient analysis codes have been developed to satisfy the demand for control strategy and accident study for s-CO 2 Brayton cycle direct or indirect cooled reactors. A transient analysis code MMS-LMR was developed to simulate the system transient and evaluate control logics for sodiumcooled fast reactor KALIMER-600 [8]. The code can simulate coolant of Sodium and CO 2 , and modules like reactor, pipe, Na-CO 2 heat exchanger, recuperator, and compressor.…”

Section: Introductionmentioning

confidence: 99%

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Development and Verification of a Transient Analysis Tool for Reactor System Using Supercritical CO₂ Brayton Cycle as Power Conversion System

Gao

Shan

2018

Science and Technology of Nuclear Installations

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Supercritical CO2 Brayton cycle is a good choice of thermal-to-electric energy conversion system, which owns a high cycle efficiency and a compact cycle configuration. It can be used in many power-generation applications, such as nuclear power, concentrated solar thermal, fossil fuel boilers, and shipboard propulsion system. Transient analysis code for Supercritical CO2 Brayton cycle is a necessity in the areas of transient analyses, control strategy study, and accident analyses. In this paper, a transient analysis code SCTRAN/CO2 is developed for Supercritical CO2 Brayton Loop based on a homogenous model. Heat conduction model, point neutron power model (which is developed for nuclear power application), turbomachinery model for gas turbine, compressor and shaft model, and PCHE type recuperator model are all included in this transient analysis code. The initial verifications were performed for components and constitutive models like heat transfer model, friction model, and compressor model. The verification of integrated system transient was also conducted through making comparison with experiment data of SCO2EP of KAIST. The comparison results show that SCTRAN/CO2 owns the ability to simulate transient process for S-CO2 Brayton cycle. SCTRAN/CO2 will become an important tool for further study of Supercritical CO2 Bryton cycle-based nuclear reactor concepts.

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Section: Basic Model Of Compressormentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Development and Verification of a Transient Analysis Tool for Reactor System Using Supercritical CO₂ Brayton Cycle as Power Conversion System

Gao

Shan

2018

Science and Technology of Nuclear Installations

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“…Its application area has extended to the industries of nuclear [2], fossil fuel, waster heat, solar energy [3,4], etc. In the role of power conversion system for nuclear energy, the conceptual studies of S-CO 2 Brayton cycle working as direct cooling system have been widely carried out for the 2400 MW th fast reactor [5], 200 MW th gas fast reactor (SC-GFR) [6], and 36.2 MW th micro modular reactor [7,8] and also as an indirect cooling system of small modular sodium-cooled fast reactor [9,10] and lead fast reactor [11]. All these studies are preliminary feasibility analyses of Brayton cycle working with nuclear application, which is summarized in the paper of Pan Wu [12].…”

Section: Introductionmentioning

confidence: 99%

Supercritical CO₂ Brayton Cycle Design for Small Modular Reactor with a Thermodynamic Analysis Solver

Gao

Zhang

et al. 2020

Science and Technology of Nuclear Installations

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Coupling supercritical carbon dioxide (S-CO 2 ) Brayton cycle with Gen-IV reactor concepts could bring advantages of high compactness and efficiency. is study aims to design proper simple and recompression S-CO 2 Brayton cycles working as the indirect cooling system for a mediate-temperature lead fast reactor and quantify the Brayton cycle performance with different heat rejection temperatures (from 32°C to 55°C) to investigate its potential use in different scenarios, like arid desert areas or areas with abundant water supply. High-efficiency S-CO 2 Brayton cycle could offset the power conversion efficiency decrease caused by low core outlet temperature (which is 480°C in this study) and high compressor inlet temperature (which varies from 32°C to 55°C in this study). A thermodynamic analysis solver is developed to provide the analysis tool. e solver includes turbomachinery models for compressor and turbine and heat exchanger models for recuperator and precooler. e optimal design of simple Brayton cycle and recompression Brayton cycle for the lead fast reactor under water-cooled and dry-cooled conditions are carried out with consideration of recuperator temperature difference constraints and cycle efficiency. Optimal cycle efficiencies of 40.48% and 35.9% can be achieved for the recompression Brayton cycle and simple Brayton cycle under water-cooled condition. Optimal cycle efficiencies of 34.36% and 32.6% can be achieved for the recompression Brayton cycle and simple Brayton cycle under dry-cooled condition (compressor inlet temperature equals to 55°C). Increasing the dry cooling flow rate will be helpful to decrease the compressor inlet temperature. Every 5°C decrease in the compressor inlet temperature will bring 1.2% cycle efficiency increase for the recompression Brayton cycle and 0.7% cycle efficiency increase for the simple Brayton cycle. Helpful conclusions and advises are proposed for designing the Brayton cycle for mediate-temperature nuclear applications in this paper.

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“…Argonne National Laboratory (ANL) [37] and KAERI [38] proposed them for Generation IV designs and KAERI included them in an experimental helium loop to test a design for a fusion reactor based on an helium cooled molten lithium (HCML) blanket [39]. A benchmarking survey with actual prototypes of reactors can be found in [40], with thermal effectiveness from 92 % to 98.7 %; SNL [41] supports their use for both recuperators, heat entry to the power cycle and heat rejection from the cycle, highlighting the benefits of PCHE compactness; Mito et al [42] draw attention to the reduced pressure drop and Gezelius [43] gave ratios of 58 to 98 MW/m 3 for PCHE against 6.2 MW/m 3 with shell and tube heat exchangers working at the same capacity and log mean temperature difference.…”

Section: Introductionmentioning

confidence: 99%

Supercritical CO2 Brayton power cycles for DEMO (demonstration power plant) fusion reactor based on dual coolant lithium lead blanket

Linares

Cantizano

Moratilla

et al. 2016

Energy

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Fusion energy is one of the most promising solutions to the world's energy supply. This paper presents an exploratory analysis of the suitability of supercritical CO 2 Brayton power cycles as alternative energy conversion systems for a future fusion reactor based on a dual coolant lithium-lead (DCLL) blanket, as prescribed by EUROfusion. The main issue dealt is the optimization of the integration of the different thermal sources with the power cycle (up to four at different power and temperature levels) in order to achieve the highest electricity production. The analysis includes the assessment of the pumping consumption both in the source loops as in the sink one. Other considerations, as control issues and integration of thermal energy storage systems to face the pulsed operation, have been also taken intoaccount. An exergy analysis has been performed in order to understand the behavior of each layout.Up to ten scenarios have been analyzed, taking into account the heat power released from some thermal sources directly to the sink and assessing different locations for thermal sources heat exchangers.Neglecting the worst four scenarios, it is observed less than 2% of variation among the other six ones.One of the best six scenarios clearly stands out over the others due to the location of the thermal sources in a unique island, being this scenario compatible with the control criteria. In this proposal 34.6% of electric efficiency (before the self-consumptions of the reactor but including pumping consumptions and generator efficiency) is achieved.KEYWORDS: balance of plant, fusion power, supercritical CO 2 Brayton cycle, DCLL, DEMO Highlights:> Supercritical CO 2 Brayton cycles have been proposed for BoP of DCLL fusion reactor.> Integration of different available thermal sources has been analyzed considering ten scenarios.> Neglecting the four worst scenarios the electricity production varies less than 2%. > Control and energy storage integration issues have been considered in the analysis. > Discarding the vacuum vessel and joining the other sources in an island is proposed.-3 -

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DEVELOPMENT OF A SUPERCRITICAL CO₂BRAYTON ENERGY CONVERSION SYSTEM COUPLED WITH A SODIUM COOLED FAST REACTOR

Cited by 67 publications

References 2 publications

Development and Verification of a Transient Analysis Tool for Reactor System Using Supercritical CO₂ Brayton Cycle as Power Conversion System

Development and Verification of a Transient Analysis Tool for Reactor System Using Supercritical CO₂ Brayton Cycle as Power Conversion System

Supercritical CO₂ Brayton Cycle Design for Small Modular Reactor with a Thermodynamic Analysis Solver

Supercritical CO2 Brayton power cycles for DEMO (demonstration power plant) fusion reactor based on dual coolant lithium lead blanket

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DEVELOPMENT OF A SUPERCRITICAL CO2BRAYTON ENERGY CONVERSION SYSTEM COUPLED WITH A SODIUM COOLED FAST REACTOR

Cited by 67 publications

References 2 publications

Development and Verification of a Transient Analysis Tool for Reactor System Using Supercritical CO2 Brayton Cycle as Power Conversion System

Development and Verification of a Transient Analysis Tool for Reactor System Using Supercritical CO2 Brayton Cycle as Power Conversion System

Supercritical CO2 Brayton Cycle Design for Small Modular Reactor with a Thermodynamic Analysis Solver

Supercritical CO2 Brayton power cycles for DEMO (demonstration power plant) fusion reactor based on dual coolant lithium lead blanket

Contact Info

Product

Resources

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DEVELOPMENT OF A SUPERCRITICAL CO₂BRAYTON ENERGY CONVERSION SYSTEM COUPLED WITH A SODIUM COOLED FAST REACTOR

Development and Verification of a Transient Analysis Tool for Reactor System Using Supercritical CO₂ Brayton Cycle as Power Conversion System

Development and Verification of a Transient Analysis Tool for Reactor System Using Supercritical CO₂ Brayton Cycle as Power Conversion System

Supercritical CO₂ Brayton Cycle Design for Small Modular Reactor with a Thermodynamic Analysis Solver