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DEVELOPMENT OF A SUPERCRITICAL CO2 BRAYTON ENERGY CONVERSION SYSTEM COUPLED WITH A SODIUM COOLED FAST REACTOR SCIE SCOPUS KCI

Title
DEVELOPMENT OF A SUPERCRITICAL CO2 BRAYTON ENERGY CONVERSION SYSTEM COUPLED WITH A SODIUM COOLED FAST REACTOR
Authors
Cha, JELee, THEoh, JHSeong, SHKim, SOKim, DEKim, MHKim, TWSuh, KY
Date Issued
2009-10
Publisher
KOREAN NUCLEAR SOC
Abstract
Systematic research has been conducted by KAERI to develop a supercritical carbon dioxide Brayton cycle energy conversion system coupled with a sodium cooled fast reactor. For the development of the supercritical CO2 Brayton cycle ECS, KAERI researched four major fields, separately. For the system development, computer codes were developed to design and analyze the supercritical CO2 Brayton cycle ECS coupled with the KALIMER-600. Computer codes were developed to design and analyze the performance of the major components such as the turbomachinery and the high compactness PCHE heat exchanger. Three dimensional flow analysis was conducted to evaluate their performance. A new configuration for a PCHE heat exchanger was developed by using flow analysis, which showed a very small pressure loss compared with a previous PCHE while maintaining its heat transfer rate. Transient characteristics for the supercritical CO2 Brayton cycle coupled with KALIMER-600 were also analyzed using the developed computer codes. A Na-CO2 pressure boundary failure accident was analyzed with a computer code that included a developed model For the Na-CO2 chemical reaction phenomena. The MMS-LMR code was developed to analyze the system transient and control logic. Oil the basis of the code, the system behavior was analyzed when a turbine load was changed. This paper contains the current research overview of the supercritical CO2 Brayton cycle coupled to the KALIMER-600 as an alternative energy conversion system.
Keywords
Supercritical CO2; Brayton Cycle; Energy Conversion System; SFR; KALIMER-600; PCHE
URI
https://oasis.postech.ac.kr/handle/2014.oak/26462
DOI
10.5516/NET.2009.41.8.1025
ISSN
1738-5733
Article Type
Article
Citation
NUCLEAR ENGINEERING AND TECHNOLOGY, vol. 41, no. 8, page. 1025 - 1044, 2009-10
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