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ANSYS를 이용한 개량핵연료 집합체 상세모델 개발에 관한 연구
전상윤(Jeon Sang-Youn),전경락(Jeon Kyeong-Lak),이영신(Lee Young-Shin) 대한기계학회 2004 대한기계학회 춘추학술대회 Vol.2004 No.10
The fuel assembly seismic and LOCA analyses are performed to verify that the stresses of fuel assembly components will be within its allowable stress and/or maintain coolable geometry so as to assure a safe shutdown of the reactor. The fuel assembly core model for seismic and LOCA analysis is accomplished by simplified spring-mass model, which is established using fuel assembly detailed model. The fuel assembly detailed model is usually established by using a fuel vendor's special computer program. In this study, the fuel assembly detailed model using a commercial finite element analysis program, ANSYS, was established to replace WECAN finite element program of Westinghouse Electric Co. for fuel assembly seismic and LOCA analysis. To verify ANSYS model, fuel assembly modal analyses were performed and the results were compared with the WECAN analysis results and the fuel assembly mechanical test results. The differences of analysis results between ANSYS and WECAN model were less than 1% and the analysis results are well coincident with the test results.
웨스팅하우스형 원전용 개량핵연료 ACE7™의 노내 연소성능
장영기(Young Kim Jang),전경락(Kyeong Lak Jeon) 대한기계학회 2010 대한기계학회 춘추학술대회 Vol.2010 No.5
Advanced nuclear fuels of ACE7™ which were developed for 16×16 and 17×17 Westinghouse type nuclear power plants completed their in-reactor verification tests in 2008 and 2009. The targets were to develop advanced fuels from the economy and safety points of view in comparison to the nuclear fuels being supplied currently. Three times of assembly-wise inspections after each cycle and rod-wise inspections after discharge using the ACE7™ Lead Test Assemblies (LTAs) were performed in Kori units 2&3. The results of the evaluation confirmed to meet their design criteria. The 16ACE7™ started to supply to Kori unit 2 from 2008 and the 17ACE7™ started to supply 17×17 Westinghouse type plants starting Kori unit 4 from 2009 commercially, respectively. The hot cell examinations on ACE7T LTA rods and skeleton are being prepared for further verification in detail. These fuels are also being examined continuously through the surveillance programs during the region implementation.
유영균(Young Gyun Yoo),김재훈(Jae Hoon Kim),이현승(Hyun Seung Lee),박진무(Jin Moo Park),박준규(Joon Kyoo Park),전경락(Kyeong lak Jeon) 대한기계학회 2010 대한기계학회 춘추학술대회 Vol.2010 No.11
Spacer grid is key-component to support fuel rod in nuclear fuel assembly. Contacting force from spring and dimple and fluid influenced vibration damage to fuel rod and spacer grid. In the study, the stress analysis of spacer grid performed under environment of inside the reactor. And the characteristic of stress distribution evaluated by boundary condition that suitable for this analysis.