Thermohydraulic design analysis of PWR U-tube steam generator = 가압 경수형 원자력 발전소에 사용되는 U-TUBE 증기 발생기의 열수력적 설계분석

A computer code, USDA(U - tube Steam Generator Design Analysis Code) for U - tube steam generator design analysis was developed on the basis of the PWR core transient analysis code, THERMIT. The fluid model, which is based on three - dimensional, nonlinear, and two fluid conservation equations for mass, energy and momentum, can account for both compressibility and thermal expansion of fluid flow. The numerical scheme is characterized by the ICE (Implicit Continuous - fluid Eulerian) method and semi - implicit method. In the present work, the original ($x, y, z$) coordinates used in THERMIT were transformed to the cylindrical coordinates ($r,\theta, z$) which are better fitted in the geometry of steam generators. The recirculation flow model was developed to implement the downcomer. The model was developed to account for the U - bend frictional pressure drop by coordinates transformation, which uses the natural geometry coordinates of the U - bend region. Sample calculation was done by using simulation experiments performed by EPRI to check the code.
Advisors
No, Hee-Cheonresearcher노희천researcher
Publisher
한국과학기술원
Issue Date
1984
Identifier
64338/325007 / 000821253
Language
eng
Description

학위논문(석사) - 한국과학기술원 : 핵공학과, 1984.2, [ 1책(면수복잡) ]

Keywords

핵증기 발생기.

URI
http://hdl.handle.net/10203/49078
Link
http://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=64338&flag=t
Appears in Collection
NE-Theses_Master(석사논문)
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