• 제목/요약/키워드: KAERI

검색결과 1,550건 처리시간 0.041초

Flow-accelerated corrosion assessment for SA106 and SA335 pipes with elbows and welds

  • Kim, Dong-Jin;Kim, Sung-Woo;Lee, Jong Yeon;Kim, Kyung Mo;Oh, Se Beom;Lee, Gyeong Geun;Kim, Jongbeom;Hwang, Seong-Sik;Choi, Min Jae;Lim, Yun Soo;Cho, Sung Hwan;Kim, Hong Pyo
    • Nuclear Engineering and Technology
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    • 제53권9호
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    • pp.3003-3011
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    • 2021

  • A FAC (flow-accelerated corrosion) test was performed for a straight pipe composed of the SA335 Gr P22 and SA106 Gr B (SA106-SA335-SA106) types of steel with welds as a function of the flow rate in the range of 7-12 m/s at 150 ℃ and with DO < 5 ppb at pH levels ranging from 7 to 9.5 up to a cumulative test time of 7200 h using the FAC demonstration test facility. Afterward, the experimental pipe was examined destructively to investigate opposite effects as well as entrance effects. In addition, the FAC rate obtained using a pipe specimen with a 50 mm inner diameter was compared with the rate obtained from a rotating cylindrical electrode. The effects of the complicated fluid flows at the elbow and orifice of the pipeline were also evaluated using another test section designed to examine the independent effects of the orifice and the elbow depending on the distance and the combined effects on orifice and elbow. The tests were performed under the following conditions: 130-150 ℃, DO < 5 ppb, pH 7 and a flow rate of 3 m/s. The FAC rate was determined using the thickness change obtained from commercial room-temperature ultrasonic testing (UT).

  • https://doi.org/10.1016/j.net.2021.03.026 인용 PDF KSCI

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

  • Cha, Jae-Eun;Lee, Tae-Ho;Eoh, Jae-Hyuk;Seong, Sung-Hwan;Kim, Seong-O;Kim, Dong-Eok;Kim, Moo-Hwan;Kim, Tae-Woo;Suh, Kyun-Yul
    • Nuclear Engineering and Technology
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    • 제41권8호
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    • pp.1025-1044
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    • 2009

  • 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 $CO_2$ Brayton cycle ECS, KAERI researched four major fields, separately. For the system development, computer codes were developed to design and analyze the supercritical $CO_2$ 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 $CO_2$ Brayton cycle coupled with KALIMER-600 were also analyzed using the developed computer codes. A Na-$CO_2$ pressure boundary failure accident was analyzed with a computer code that included a developed model for the Na-$CO_2$ chemical reaction phenomena. The MMS-LMR code was developed to analyze the system transient and control logic. On 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 $CO_2$ Brayton cycle coupled to the KALIMER-600 as an alternative energy conversion system.

  • https://doi.org/10.5516/NET.2009.41.8.1025 인용 PDF KSCI

한국원자력연구소에서 개발한 가압경수로용 핵연료 지지격자의 기계/구조적 성능 해석 및 시험 (Mechanical/Structural Performance Analysis and Test on the KAERI Designed Spacer Grids for the PWR)

  • 송기남;윤경호;강흥석;최명환
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2003년도 추계학술대회
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    • pp.1297-1302
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    • 2003

  • KAERI has contrived 15 kinds of spacer grid shapes of its own since 1997 and applied for domestic and foreign patents. To date, KAERI has obtained US and ROK patents for 6 kinds of spacer grid shapes among them and the others are under review in USA, EC, China, and ROK. In this study, mechanical/structural performance analysis and test on two spacer grid shapes that are assumed to be the most effective candidates for the spacer grid of the next generation nuclear fuel in Korea was carried out. The result has shown that the performances of the candidates are better or not worse than those of the current spacer grid.

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