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최명환(Choi, M.H.),주기남(Choo, K.N.),조만순(Cho, M.S.),김봉구(Kim, B.G.) 한국소음진동공학회 2005 한국소음진동공학회 논문집 Vol.15 No.12
The bottom structure of an instrumented capsule is a part which is joined at the receptacle of the flow tube in the reactor in-core. A geometrical change of the bottom structure has an effect on the pressure drop and the vibration of the capsule. The out-pile test to evaluate the structural integrity of the material capsule called 04M-17U was performed by using a single channel and a half core test loop. From the pressure drop test, the optimized diameter of the cone shape's bottom structure which satisfies HANARO's flow requirement (19.6 kg/s) is 71 mm. The maximum displacement of the capsule measured at the half core test loop is lower than 1.0 mm. From the analysis results, it is found that the test hole will not be interfered with near the flow tubes because its displacement due to the cooling water is very small at 0.072 mm. The fundamental frequency of the capsule under water is 9.64 Hz. It is expected that the resonance between the capsule and the fluid flow due to the cooling water in HANARO's in-core will not occur. Also, the new bottom structure of a solid cone shape with 71 mm in diameter will be applicable to the material and special capsules in the future.
벨로우즈를 이용한 반복 하중부과장치의 개발 및 성능시험
최명환(M.H. Choi),조만순(M.S. Cho),김봉구(B.G. Kim),김학노(H.R. Kim) 대한기계학회 2006 대한기계학회 춘추학술대회 Vol.2006 No.6
A fatigue capsule is one of the special capsules to investigate the fatigue characteristics of the nuclear materials in a research reactor, HANARO. In this study, the performance test and the preliminary fatigue test results by using a cyclic load device newly developed for a fatigue capsule are described. In order to obtain the characteristics such as a realization and a controllability of the periodic wave shape and the relation between the pressure and the load, a spring and rigid bar specimens are used. The fatigue test for the STS 316L specimen with 1.8㎜ in diameter and 12.5㎜ in gage length is also performed under the same conditions as the temperature(550℃) of the specimen during irradiation tests. As a result of the test, the fracture of the specimen occurs at a total of 127,865 cycles (22 days), and the displacement is 2.63㎜. It is expected that these results will be used for a determination of test conditions and a comparison of the in-pile fatigue test results.
최명환(M. H. Choi),조영갑(Y. G. Cho),김정현(J. H. Kim),이관희(K. H. Lee) 한국소음진동공학회 2015 한국소음진동공학회 논문집 Vol.25 No.12
A control rod drive mechanism(CRDM) is a reactor regulating system, which inserts, withdraws or maintains a control rod containing a neutron absorbing material within a reactor core to control the reactivity of the core. The top-mounted CRDM for Jordan Research and Training Reactor(JRTR) with 5 MW power has been designed and fabricated based on the HANARO’s experience through KAERI and DAEWOO consortium project. This paper describes the performance qualification test results to demonstrate the operability of a prototype and four production CRDMs during the reactor lifetime. The driving performance, the drop performance and the endurance tests for CRDM are carried out at a test rig simulating the actual reactor conditions. A vibration of internal components due to the coolant flow is also measured using a laser vibrometer. As a result, the CRDMs are driven having a good driving performance without a malfunction between command and output signals for the stepping motor. Also, the pure drop time and the impact acceleration are within 0.72 s and 4.2 g to meet the design requirements, and the vibrational displacement of control rod is measured as maximum 5.2 μm.
최명환(Choi, M.H.),김지호(Kim, J.H.),허형(Huh, H.),유제용(Yu, J.Y.) 한국소음진동공학회 2010 한국소음진동공학회 논문집 Vol.20 No.7
A control element drive mechanism(CEDM) is a reactor regulating system, which inserts, withdraws or maintains a control rod containing a neutron absorbing material within a reactor core to control the reactivity of the core. The ball-screw type CEDM for the integral reactor has a spring-damper system to reduce the impact force due to the scram of the CEDM. This paper describes the experimental results to obtain the drop and damping characteristics of the CEDM. The drop tests are performed by using a drop test rig and a facility. A drop time and a displacement after an impact are measured using a LVDT. The influences of the rod weight, the drop height and the flow area of hydraulic damper on the drop and damping behavior are also estimated on the basis of test results. The drop time of the control element is within 4.5s to meet the design requirement, and the maximum displacement is measured as 15.6 mm. It is also found that the damping system using a spring-hydraulic damper plays a good damper role in the CEDM.