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하나로 원자로에 설치될 대향 이상 열사이펀 루프에 관한 실험
황권상,조만순,성형진,Hwang, Kwon-Sang,Cho, Man-Soon,Sung, Hyung-Jin 대한기계학회 2000 大韓機械學會論文集B Vol.24 No.8
An experimental study was carried out to delineate the flow characteristics in a closed countescurrent two-phase thermo syphon with concentric tubes. This is to be installed in the HANARO research reactor as a part of a Cold Neutron Source(CNS). In the present investigation, experiments ata room temperature with Freon-II3 as a moderator were performed. Results show that, based on the magnitude of pressure fluctuation, the flow regimes could be divided into 4 distinct ones in the ($V_f,\;Q_i$) plane, where $V_f$ represents the volume of the charged liquid and $Q_i$ the heat load: a stable flow regime, an oscillatory flow regime, a restablized flow regime and a dryout flow regime. For $V_f$>2.5l, the flow is stable at low $Q_i$. However, as $Q_i$ increases, the flow becomes oscillatory and finally restablizes As $V_f$ increases, the oscillation amplitude decreases, reaching to the restablized flow region at low $Q_i$, and the liquid level in the moderator cell remains high. In the oscillatory flow regimes, for a fixed VI; the oscillating period of time varies with $Q_i$, having a minimum value at a certain value of $Q_i$. The heat load, where the oscillating period of time is minimum, decreases as $V_f$ increases.
Contribution of HANARO Irradiation Technologies to National Nuclear R&D
조기남,조만순,양성우,박상준 한국원자력학회 2014 Nuclear Engineering and Technology Vol.46 No.4
HANARO is a multipurpose research reactor located at the Korea Atomic Energy Research Institute (KAERI). Since thecommencement of its operation in 1995, various neutron irradiation facilities, such as rabbit irradiation facilities, fuel test loop(FTL) facilities, capsule irradiation facilities, and neutron transmutation doping (NTD) facilities, have been developed andactively utilized for various nuclear material irradiation tests requested by users from research institutes, universities, andindustries. Most irradiation tests have been related to national R&D relevant to present nuclear power reactors such as theageing management and safety evaluation of the components. Based on the accumulated experience as well as thesophisticated requirements of users, HANARO has recently supported national R&D projects relevant to new nuclear systemsincluding the System-integrated Modular Advanced Reactor (SMART), research reactors, and future nuclear systems. Thispaper documents the current state and utilization of irradiation facilities in HANARO, and summarizes ongoing researchefforts to deploy advanced irradiation technology.
중성자 조사에 따른 SiC Schottky Diode의 전기적 특성 변화
김성수,강민석,조만순,구상모,Kim, Sung-Su,Kang, Min-Seok,Cho, Man-Soon,Koo, Sang-Mo 한국전기전자재료학회 2014 전기전자재료학회논문지 Vol.27 No.4
The effect of neutron irradiation on the properties of SiC Schottky Diode has been investigated. SiC Schottky diodes were irradiated under neutron fluences and compared to the reference samples to study the radiation-induced changes in device properties. The condition of neutron irradiation was $3.1{\times}10^{10}$ $n/cm^2$. The current density after irradiation decreased from 12.7 to 0.75 $A/cm^2$. Also, a slight positive shift (${\Delta}V_{th}$= 0.15 V) in threshold voltage from 0.53 to 0.68 V and a positive change (${\Delta}{\Phi}_B$= 0.16 eV) of barrier height from 0.89 to 1.05 eV have been observed by the neutron irradiation, which is attributed to charge damage in the interface between the metal and the SiC layer.
단반감기 기체상 방사성추적자 활용을 위한 차폐운반용기 제작
문진호,박장근,양성우,조만순,정성희 (사)한국방사선산업학회 2020 방사선산업학회지 Vol.14 No.3
To use radioactive Ar-clathrate in industrial field, a shielding and transportationcontainers have been fabricated that can recover Ar gas with alcohol and inject it into industrialprocesses. For evaluating the shielding suitability of the transport container, a Monte Carlosimulation was performed. When 41Ar 100 mCi was transported using the container, it was lessthan 0.4 mSv·h-1 at the point where the surface dose rate was highest. In addition, as a resultof calculating the internal temperature of the Ar-clathrate during irradiating neutrons, whenirradiated at the point where the thermal neutron flux of the HANARO reactor is highest, it is77℃, so that radioactive argon gas can be stably produced without decomposition or melting ofAr-clathrate.
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.
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.