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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),강영환(Y.H. Kang),조만순(M.S. Cho),김봉구(B.G. Kim),손재민(J.M. Sohn),주기남(K.N. Choo) 대한기계학회 2009 대한기계학회 춘추학술대회 Vol.2009 No.5
An instrumented capsule has been used for an irradiation test of various nuclear materials in the research reactor, high-flux advanced neutron application reactor, HANARO. In this study, in order to estimate the results of an irradiation test for the material capsule and to obtain the preliminary design data of the new conceptual capsule using a liquid thermal media, the thermal analysis is performed by using a 2D model for each cross section including specimens. As a result of the tests and analyses, the maximum temperature at the reactor power of 24㎿ is 255℃ for an irradiation test and 260℃ for an FE analysis in the middle stage of the capsule. Also, from the comparison of the results for the capsule with Al and LBE thermal media, it is found that the conceptual design of a LBE capsule will meet the test requirements for a high temperature irradiation of new materials in the HANARO reactor.
원추형 하단부 구조를 갖는 캡슐의 하나로와의 양립성시험
최명환(M.H. Choi),조만순(M.S. Cho),주기남(K.N Choo),박승재(S.J. Park),김봉구(B.G. Kim),강영환(Y.H. Kang) 대한기계학회 2004 대한기계학회 춘추학술대회 Vol.2004 No.4
The design modification of bottom guide structures of the instrumented capsule, which is used for the irradiation test in the HANARO reactor, was required because of the trouble of the bottom guide arm's pin during irradiation. The previous structure with 3-pin arms was changed into the cone shape of one body. The specimens of the bottom end cap ring with three different sizes (φ68/70/72mm) were designed and manufactured. The out-pile tests for the capsule with previous and new three bottom guide structures were performed in the one-channel flow test facilities. In order to evaluate the compatibility with HANARO and the structural integrity of the capsule, a loading/unloading, a pressure drop, a thermal performance, a vibration, and an endurance test were conducted. From out-pile test results, the capsule with the cone shape bottom guide structures was found to be more stable than the previous structure and the optimized size of the bottom guide structure selected was 70mm in diameter. It is expected that the new bottom guide structures will be applicable to all material and special capsules which will be designed and manufactured for the irradiation tests in the future.
최명환(M.H. Choi),강흥석(H.S. Kang),송기남(K.N. Song),정연호(Y.H. Jung) 대한기계학회 2002 대한기계학회 춘추학술대회 Vol.2002 No.5
The spacer grid is one of the main structural components in the fuel assembly, which supports the fuel rods<br/> and maintains coolable geometry from an external load. A vibration test and a finite element analysis using<br/> ABAQUS on a dummy fuel rod continuously supported by Optimized H type(OHT) and New Double<br/> Plate(NDP) spacer grids are performed to obtain the vibration characteristics such as natural frequencies and<br/> mode shapes and to verify a finite element model. The results fro m the test and the finite element analysis are<br/> compared by modal assurance criteria (MAC) values. It is resulted that MACs for the first, the third and the<br/> fifth mode shapes are relatively good as compared with those of the second and fourth ones. The natural<br/> frequency differences between two methods as well as the mode comparison results for the rod with OHT<br/> spacer grid are better than those with NDP spacer grid. It is judged that the FE model for the NDP spacer grid<br/> spring should be modified to consider the long contact length which actually happen when the spring supports<br/> the rod.