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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.advisor박군철-
dc.contributor.author염수빈-
dc.date.accessioned2019-06-25T16:07:45Z-
dc.date.available2019-06-25T16:07:45Z-
dc.date.issued2012-02-
dc.identifier.other000000000562-
dc.identifier.urihttps://hdl.handle.net/10371/155228-
dc.identifier.urihttp://dcollection.snu.ac.kr/jsp/common/DcLoOrgPer.jsp?sItemId=000000000562-
dc.description학위논문 (석사)-- 서울대학교 대학원 : 에너지시스템공학부, 2012. 2. 박군철.-
dc.description.abstractThrough 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.
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dc.format.extent72-
dc.language.isoeng-
dc.publisher서울대학교 대학원-
dc.subject.ddc622.33-
dc.titleAssessment 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.alternative한국형 헬륨냉각 테스트 블랭킷의 일차벽 목업 및 헬륨 공급장치에서의 열수력 실험을 통한 시스템 코드 적용성 평가-
dc.typeThesis-
dc.typeDissertation-
dc.description.degreeMaster-
dc.contributor.affiliation에너지시스템공학부-
dc.date.awarded2012-02-
dc.contributor.major원자핵공학-
dc.identifier.holdings000000000006▲000000000011▲000000000562▲-
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