• Journal of the Korean Society for Aeronautical & Space Sciences
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• v.45 no.1
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• pp.71-78
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• 2017

The electrical power system of Korean Utility Helicopter(KUH) is designed as a dual control system to enhance the system safety of aircraft and each system is installed separately at left and right of the aircraft. The system is composed of 2 AC generators, 1 APU generator, 2 Transformer Rectifier Units(TRU), AC/DC Electrical Master Box(AC/DC EMB). The AC/DC EMB, consists of 2 AC EMB and 2 DC EMB, is essential equipment which supply and distribute electric power to the aviation electronics and electrical equipment of KUH. There were defects caused by internal short circuit in AC EMB during the first production phase of the KUH. This paper describes the analysis of the defects, troubleshooting process, root cause, and the solution by design change.

• Journal of the Korean Society of Surveying, Geodesy, Photogrammetry and Cartography
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• v.29 no.6
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• pp.601-611
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• 2011

The paper deals with the selection of 3D display devices in accordance with the user's conveniences and accuracy of spatial information by applying 3D display devices to Spatial Information Update System (SIUS) which generate edit and update digital thematic maps. After applying different manufacturer's 3D display devices to SIUS, aerial images acquired from the stereo images were displayed through the devices and spatial information was extracted from the displayed 3D images. Assessment of 3D display devices were based on quantitative and qualitative analysis on accuracy of spatial information and user's conveniences. Planar's PL2020 and Redrover's Tru3Di 3D monitor has expressed outstanding display environment in 3D related tasks for the generation of spatial information compared to other 3D display devices. System improvement is expected regarding accuracy of spatial information, work efficiency and user's conveniences.

• Tunnel and Underground Space
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• v.12 no.1
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• pp.52-69
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• 2002

The WIPP (Waste Isolation Pilot Plant), located 42km east of Carlsbad, New Mexico (NM), in bedded salt 655m below the surface, is a mined repository constructed by the US DOE for the permanent disposal of transuranic (TRU) wastes generated by activities related to defence of the US since 1970. Its historical disposal operation began in March 1999 following receipt of a final permit from the State of NM after a positive certification decision for the WIPP was issued by the EPA in 1998, as the first licensed facility in the US for the deep geologic disposal of radioactive wastes. The CCA (Compliance Certification Application) for the WIPP that the DOE submitted to the EPA in 1966 was supported by an extensive performance assessment (PA) carried out by Sandia National Laboratories (SNL), with so-called 1996 PA. Even though such PA methodologies could be greatly different from the way we consider for HLW disposal in Korea largely due to quite different geologic formations in which repository are likely to be located, a review on lots of works done through the WIPP PA studies could be the most important lessons that we can learn from in view of current situation in Korea where an initial phase of conceptual studies on HLW disposal has been just started. The objective of this art report is an overview of the methodology used in the recent WIPP PA to support the US DOE WIPP CCA and some relevant results completed by SNL.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.15 no.3
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• pp.191-197
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• 2017

The Korea Atomic Energy Research Institute (KAERI) has developed a safeguards technology for pyroprocessing based on the Safeguards-By-Design (SBD) concept. KAERI took part in a Member-State Support Program (MSSP) to establish a pyroprocessing safeguards approach. A Reference Engineering-scale Pyroprocessing Facility (REPF) concept was designed on which KAERI developed its safeguards system. Recently the REPF is being upgraded to the REPF+, a scaled-up facility. For assessment of the nuclear-material accountancy (NMA) system, KAERI has developed a simulation program named Pyroprocessing Material Flow and MUF Uncertainty Simulation (PYMUS). The PYMUS is currently being upgraded to include a Near-Real-Time Accountancy (NRTA) statistical analysis function. The Advanced Spent Fuel Conditioning Process Safeguards Neutron Counter (ASNC) has been updated as Non-Destructive Assay (NDA) equipment for input-material accountancy, and a Hybrid Induced-fission-based Pu-Accounting Instrument (HIPAI) has been developed for the NMA of uranium/transuranic (U/TRU) ingots. Currently, performance testing of Compton-suppressed Gamma-ray measurement, Laser-Induced Breakdown Spectroscopy (LIBS), and homogenization sampling are underway. These efforts will provide an essential basis for the realization of an advanced nuclear-fuel cycle in the ROK.

• Journal of Energy Engineering
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• v.13 no.2
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• pp.101-111
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• 2004

The main purpose of a liquid metal reactor core thermal-hydraulic design is to efficiently extract the core thermal power by distributing the appropriate sodium coolant flow according to the power distribution in the core. The thermal-hydraulic design procedure consists of the coolant flow distribution to the sub-assemblies, the coolant/fuel temperature calculations and detailed subchannel analysis. This paper describes the LMR core thermal-hydraulic design methodology and summarizes the major design and analysis results of KALIMER breeder and breakeven cores and subassemblies. KALIMER is a 150 MWe rated (392 MWth) heterogeneous core with U-TRU-Zr ternary alloy fuel and sodium coolant.

• Journal of rehabilitation welfare engineering & assistive technology
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• v.10 no.4
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• pp.243-249
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• 2016

In this paper, we evaluate the effectiveness of mechanical horseback riding exercise training for cardiopulmonary responses in 26 healthy adults (male 14, female 12) and suggest its clinical applicability. Exercise was performed using a mechanical horseback riding machine, JOBA(R) (Panasonic Electric Works, Osaka, Japan) and riding movement speed was increased from level 2 (0.73Hz), to 4 (0.9Hz), to 6 (1.03Hz), to 8 (1.2Hz), to 9 (1.3Hz) and maintained 3minutes in each level. Heart rate, blood pressure, maximum oxygen consumption (VO2max) were measured by respiratory gas analysis system (TruOne 2400, Parvo Medics, USA) and exercise tolerance test system(Q Stress, Cardiac Science, USA). To measure exercise intensity, metabolic equivalent (MET) were measured and percent of Heart rate reserve (%HRR), percent of peak heart rate (%peak HR) and calorie consumption were calculated. The results were analysed by SPSS 18.0. We found that the exercise intensity of mechanical horseback riding exercise using JOBA(R) for 15 minutes is moderate in healthy adult who received pre-training.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.351-357
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• 2003

Transuranic elements such as Pu, Am and Cm in synthetic solution of spent nuclear fuel samples were determined by electrodeposition followed by alpha-spectrometry after separation using anion exchange and extraction chromatography in order to determine the transuranic elements in radwaste samples from nuclear power plants. Plutonium was separated by 12M HC1-0.1M HI as an eluent on anion exchange column. As a second step Am and Cm were separated in a group by DTPA-Lactic acid as the eluent on HDEHP coated column. The nuclides of $^{239}Pu$, $^{241}Am$및 $^{244}Cm$ separated were determined by alpha-spectrometry after electrodeposition in 0.1M $NaHSo_4$-0.53M $Na_2SO_4$buffer solution as an electrolyte. The recovery yields of $^{239}Pu$, $^{241}Am$및 $^{244}Cm$ were 83.8%, 85.2% and 86.3%, respectively, from the synthetic solution containing uranium and non-radioactive metal elements.

• The Journal of Korean Institute of Electromagnetic Engineering and Science
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• v.25 no.2
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• pp.217-222
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• 2014

This paper discusses about the beam pattern distortion caused by the failures of some antenna modules in the active array antenna and analyses the possibility of improvement through applying the beam pattern compensation method previously studied. The beam pattern distortion which is mostly represented as an increase of the sidelobe level, can be suppressed through re-synthesizing each module's magnitude and phase. This method was applied to the prototype of active array antenna system, and the results of antenna pattern distortion and compensation were analyzed and measured in the Near Field Chamber. Array failures are generally divided into random TR module failures and TRU(TR Unit: combination of TR modules, Beam Computation module, Power supply module) failures. The results of beam pattern compensation were analyzed in each failure and compared to the results of the simulation. The beam pattern compensation results applied to the real active antenna array system showed the similar to the simulation results. Consequently, it was verified the beam pattern could be compensated with the magnitude and phase adjustment of other normal antenna modules.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2009.06a
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• pp.253-253
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• 2009

전세계적 고유가 및 $CO_2$ 배출로 인한 지구 온난화 문제 동 앞으로의 에너지 개발은 지속가능하며, 환경친화적이어야 한다. 따라서 가장 값싼 에너지원의 하나이며, 또한 환경문제에서도 유리한 원자력 에너지에 대한 세계적인 관심이 지난 약 30년 정도의 침체기간을 거친후 미국, 중국, 인도, 유럽, 아시아 등을 중심으로 다시 부활하고 있다. 그러나 미래 원자력에너지의 활발한 이용 및 지속 가능성을 위해서는 고준위 방사성 폐기물의 처리문제가 반드시 해결되어야 하며, 그 중에서도 사용후핵연료의 관리문제는 원자력 발전소의 계속 운전을 위해 시급히 해결되어야 한다. 한국원자력연구원도 2008년 12월 결정된 정부의 "미래 원자력시스템 개발 Action Plan" 을 통해 이러한 사용후핵연료의 관리문제를 해결하기 위한 연구 과제를 10여년 동안 수행해오고 있으며, 그 중 하나가 파이로(Pyroprocess) 공정개발이다. 1997년부터 관련연구가 착수되어, 2001년부터는 약 6년간에 걸쳐 파이로의 전처리 공정 및 전해환원 공정에 대한 실험실 규모 실증시설인 ACPF(Advanced spent fuel Conditioning Process Facility)를 개발한 바 있다. 또한 향후 파이로 기술의 상용화를 위해 2016년 까지 약 10톤/년 규모의 공학규모 파이로 실증시설(ESPF)을 건설하고 이를 기초로 2025년까지 100톤/년 규모의 파이로 상용시설 (KAPF) 을 건설하여 여기서 나온 우라늄 및 TRU 물질을 이용해 2030년까지 개발 예정인 소듐냉각 고속로에 필요한 핵연료를 제작, 공급하는 계획을 가지고 있다. 이 논문에서는 파이로 시설개발의 가장 중요한 인자중 하나인 시설의 안전성 확보를 위해 외국 및 국내에서의 연구개발 현황을 알아보고 안전성 분석 및 평가방법에 대한 기본 인자들을 도출해 보았다. 또한 파이로 시설의 인허가를 위한 사용후핵연료 처리시설 규제관련 국, 내외의 연구현황도 알아보았다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.8 no.1
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• pp.9-17
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• 2010

The LCC (Liquid Cadmium Cathode) structure to be developed for inhibiting the formation and growth of the uranium dendrite has been known as a key part in the electrowinning process for the simultaneous recovering of uranium and TRU (TRans Uranium) elements from spent fuels. A zinc-gallium (Zn-Ga) experimental system which is able to be functional in aqueous condition and normal temperature has been set up to observe the formation and growth phenomena of the metal dendrites on liquid cathode. The growth of the zinc dendrites on the gallium cathode and the performance of the existing stirrer type and pounder type cathode structure were observed. Although the mechanical strength of the dendrites appeared to be weak in the electrolyte and easily crashed by the various cathode structures, it was difficult to effectively submerge the dendrite into the bottom of the liquid cathode. Based on the results of the aqueous phase experiments, a lab-scale electrowinning experimental apparatus which are applicable to the development of LCC srtucture for the electrowinning process was established and the performance tests of the different types of LCC structure were conducted to prohibit the uranium dendrite growth on LCC surface. The experimental results of the stirrer type LCC structures have shown that they could not effectively remove the uranium dendrites growing at the inner side of the LCC crucible and the performances of the paddle and harrow type LCC structure were similar. Therefore a mesh type LCC structure was developed to push down the uranium dendrites to the bottom of the LCC crucible growing on the LCC surface and at the inner side of the crucible. From the experimental results for the performance test of the mesh type LCC structure, the uranium was recovered over 5 wt% in cadmium without the growth of uranium dendrites. After completion of the experiments, solid precipitates of the bottom of the LCC crucible were identified as an intermetallic compound (UCd11) by the chemical analysis.