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Assessment of the system code through thermal-hydraulic test with He supplying system using the first wall mockup for the Korean He cooled test blanket : 한국형 헬륨냉각 테스트 블랭킷의 일차벽 목업 및 헬륨 공급장치에서의 열수력 실험을 통한 시스템 코드 적용성 평가
DC Field | Value | Language |
---|---|---|
dc.contributor.advisor | 박군철 | - |
dc.contributor.author | 염수빈 | - |
dc.date.accessioned | 2019-06-25T16:07:45Z | - |
dc.date.available | 2019-06-25T16:07:45Z | - |
dc.date.issued | 2012-02 | - |
dc.identifier.other | 000000000562 | - |
dc.identifier.uri | https://hdl.handle.net/10371/155228 | - |
dc.identifier.uri | http://dcollection.snu.ac.kr/jsp/common/DcLoOrgPer.jsp?sItemId=000000000562 | - |
dc.description | 학위논문 (석사)-- 서울대학교 대학원 : 에너지시스템공학부, 2012. 2. 박군철. | - |
dc.description.abstract | Through consideration of the requirements for a DEMO-relevant blanket concept,Korea (KO) has proposed a He Cooled Molten Lithium (HCML) Test Blanket Module (TBM) for testing in the International Thermonuclear Experimental Reactor (ITER). The performance analysis for thermal-hydraulics and safety analysis for an accident caused by loss of a coolant for the KO TBM have been carried out with a commercial CFD code, ANSYS-CFX and system code,GAMMA (GAs Multicomponent Mixture Analysis). In order to verify the codes,the preliminary study was performed by Lee with a single TBM First Wall (FW) mock-up made from the same material as the KO TBM, ferritic martensitic steel,using the 6 MPa nitrogen gas loop. The test was performed at pressures of 11, 19
and 29 bar and under various flow rates ranging from 0.63 to 2.44 kg/min with a constant wall temperature condition. In the present study, several points in experiment were modified for satisfying KO TBM condition; adopting constant wall heat flux condition using high heat load test facility and using helium as a coolant etc. A thermal-hydraulic test was performed with the newly constructed He loop, in which the design pressure and temperature were 9 MPa and 500 oC, respectively. In the experiment, the same mock-up was used but the number of installed thermocouples was increased from 8 to 17 to enhance the accuracy of validation for CFX-11.0. And the test was performed under the conditions of 8 MPa pressure, and 70m/s velocity, which are the same conditions of the KO TBM FW. One-side of the mock-up was heated with constant heat flux, 0.5 MW/m2 using graphite heating system KoHLT-2(Korea Heat Load Test Facility-2). The wall temperatures were measured by installed thermocouples and they show a strong parity with codes results simulated with the same test conditions. By the aid of CFX-11, heat transfer coefficient was calculated from experiment. And this result was compared with the heat transfer coefficient from GAMMA output. Through the comparison, it was found that 2 results have different tendency with one another. And because GAMMA code adapts Dittus-Boelter correlation for analyzing heat transfer phenomena, and using the film temperature not bulk temperature, 2 code calculations showed different results. After confirming these problems, modification of GAMMA code was performed. And modified GAMMA code showed good agreement with CFX-11.0 results. | - |
dc.format.extent | 72 | - |
dc.language.iso | eng | - |
dc.publisher | 서울대학교 대학원 | - |
dc.subject.ddc | 622.33 | - |
dc.title | Assessment of the system code through thermal-hydraulic test with He supplying system using the first wall mockup for the Korean He cooled test blanket | - |
dc.title.alternative | 한국형 헬륨냉각 테스트 블랭킷의 일차벽 목업 및 헬륨 공급장치에서의 열수력 실험을 통한 시스템 코드 적용성 평가 | - |
dc.type | Thesis | - |
dc.type | Dissertation | - |
dc.description.degree | Master | - |
dc.contributor.affiliation | 에너지시스템공학부 | - |
dc.date.awarded | 2012-02 | - |
dc.contributor.major | 원자핵공학 | - |
dc.identifier.holdings | 000000000006▲000000000011▲000000000562▲ | - |
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