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보일러용 3way valve 내장형 rotoless 전자식 순환펌프 시스템의 개발
한지웅(J.W.Han),금성민(S.M.Kum),유병희(B.H.Ryu),이창언(C.E.Lee),오수철(S.C.Ohu),임장순(J.S.Yim) 한국태양에너지학회 1996 한국태양에너지학회 논문집 Vol.16 No.2
본 연구는 가정용 가스 보일러 순환펌프의 문제점 보완은 물론 펌프 외부에 설치되어 있는 3way valve를 하우징 내부에 부착한 3way valve 내장형 펌프 하우징을 개발하기 위한것이다. 기존 하우징이 부착된 canned type 순환펌프의 실험결과를 근거로 3way valve 내장형 하우징을 설계 제작하였으며 신형 하우징이 부착된 canned type 순환펌프의 성능실험 및 보일러 전체 시스템에서의 순환펌프 성능 실험을 실시하였다.<br/> 실험 결과 신형 3way valve 내장형 하우징을 부착할 경우 펌프의 총양정은 평균 1~1.7m, 펌프효율은 약 25%정도 높게 나타났으며 축동력은 약 4W 감소하였다. 특히 하우징의 중량은 1.4kg에서 0.4kg으로 줄어들었고 제작비는 개당 약 5000원정도 절감할수 있었으며 조립공정의 단축으로 생산비용은 보일러 1대당 약 2만원 정도의 원가절감을 예상할수 있다. The purpose of research is to complement the circulating pump of gas boiler for the domestic and to develop a pump housing with internal three way valve: Housing and three way valve have been apart in the existing pump system.<br/> Based on the experimental result on can-typed circulating pump with existing housing, a new housing with internal three way valve was designed and manufactured. The performance of can-typed circulating pump with the new housing, and the performance of circulating pump of boiler system were tested. As a result on the test, the new housing with internal three way valve has been excellent in respect of pump performance, weight and manufacturing cost. So it is expected to have an effect of import substitution.
대와동모사법을 사용한 고속로 상부플레넘에서의 thermal striping 해석
최석기(S.K. Choi),한지웅(J.W. Han),김대희(D. Kim),이태호(T.H. Lee) 한국전산유체공학회 2014 한국전산유체공학회 학술대회논문집 Vol.2014 No.11
A computational study of a thermal striping in the upper plenum of PGSFR(Prototype Generation-IV Sodium-cooled Fast Reactor) being developed at the KAERI(Korea Atomic Energy Research Institute) is presented. The LES(Large Eddy Simulation) approach is employed for the simulation of thermal striping in the upper plenum of the PGSFR. The LES is performed using the WALE (Wall-Adapting Local Eddy-viscosity) model. More than 4.0 million unstructured numerical grids are generated in upper plenum region of the PGSFR using the CFX-Mesh commercial code. From these results, the time-averaged velocity components and temperature field in the complicated upper plenum of the PGSFR are calculated. The time history of temperature fluctuation at the dozen locations of solid walls of UIS(Upper Internal Structure), Control Rod Shroud Tube and IHX(Intermediate Heat eXchanger) are compared with both results and are additionally stored. It has been confirmed that the most vulnerable regions to thermal striping are the first plate of UIS and the flow hole at the side of UIS. From the temporal variation of temperature at the solid walls, it was possible to find the locations where the thermal stress is large and need to assess whether the solid structures can endure the thermal stress during the reactor life time.
소듐냉각고속로 상부내부구조물 열스트라이핑 거동 수치해석 연구
최선락(S.R. Choi),김대희(D. Kim),정요한(Y. Jung),최석기(S.K. Choi),한지웅(J.W. Han) 한국전산유체공학회 2019 한국전산유체공학회지 Vol.24 No.2
The Korea Atomic Energy Research Institute (KAERI) has performed a reactor design with the final goal of constructing the PGSFR (Prototype Gen-IV Sodium-cooled Fast Reactor). The main objective of the PGSFR is to verify TRU metal fuel performance, reactor operation, and transmutation ability of high-level wastes. In the PGSFR, each subassembly has an independent flow path and is separately assigned a flow rate. Therefore, outlet temperatures between adjacent subassemblies are different from each other. Coolant mixing with different temperatures causes temperature fluctuations in a structure surface near the core exit. This phenomenon is called thermal striping, which can induce periodic thermal fatigues and deteriorate the integrity of the structures. The thermal striping in the UIS (upper internal structure) of the PGSFR is evaluated by the LES model. This model is employed to characterize fast turbulent vortices generated from the core exit. Temperature fluctuation is observed along a mixing region between two adjacent assemblies. The maximum temperature fluctuation on the solid surface occurs at the CRDM guide tube tip of the outer control assembly in the core outward direction. The maximum RMS value of the temperature fluctuation at the solid surface is 18.3% of the temperature difference. The present CFD analysis will be employed to evaluate creep-fatigue damage due to the temperature fluctuation cycles in the UIS.
대와동모사법을 사용한 고속로 상부플레넘에서의 thermal striping 해석
최석기(S. K. Choi),한지웅(J. W. Han),김대희(D. Kim),이태호(T. H. Lee) 한국전산유체공학회 2014 한국전산유체공학회지 Vol.19 No.4
A computational study of a thermal striping in the upper plenum of PGSFR(Prototype Generation-IV Sodium-cooled Fast Reactor) being developed at the KAERI(Korea Atomic Energy Research Institute) is presented. The LES(Large Eddy Simulation) approach is employed for the simulation of thermal striping in the upper plenum of the PGSFR. The LES is performed using the WALE (Wall-Adapting Local Eddy-viscosity) model. More than 19.7 million unstructured elements are generated in upper plenum region of the PGSFR using the CFX-Mesh commercial code. The time-averaged velocity components and temperature field in the complicated upper plenum of the PGSFR are presented. The time history of temperature fluctuation at the eight locations of solid walls of UIS(Upper Internal Structure) and IHX(Intermediate Heat eXchanger) are additionally stored. It has been confirmed that the most vulnerable regions to thermal striping are the first plate of UIS. From the temporal variation of temperature at the solid walls, it was possible to find the locations where the thermal stress is large and need to assess whether the solid structures can endure the thermal stress during the reactor life time.