• 에너지공학
• /
• 제21권2호
• /
• pp.133-137
• /
• 2012

청정에너지 이용 기술 중 태양 에너지 이용 기술은 태양광 발전이나 태양열 난방 및 급탕 등 여러 분야에서 활용되고 이다. 특히, 획기적인 에너지 변환 방법인 열음향(Thermoacoustic)은 태양열 및 주변의 폐열을 이용하기 때문에 청정에너지 기술로서 주목받고 있다. 따라서 본 연구에서는 태양 에너지를 열원으로 하는 열음향 레이저의 개발을 위하여, 열음향파 발생 시스템에 전원을 공급하여 단일 튜브의 기하학적 형상에 따른 음향파의 기본 특성을 측정하였다. 본 연구는 스택의 재질 및 형상과 공명튜브의 내경(20.2 mm)을 고정하고, 스택의 위치와 길이, 공명튜브의 길이, 전원의 크기를 변화시켜 실험을 진행하였다. 실험 결과, 공명튜브의 길이가 200 mm, 스택의 길이가 25.6 mm이고, 스택의 위치가 닫힌 면으로부터 5 cm에 위치하였을 때 114.5 dB의 평균음압이 발생하였으며, 공급 전원을 35W로 변화시켰을 때 117.29 dB의 평균음압이 발생하였고, 각각 500 Hz의 주파수가 발생하였다. 또한 공명 튜브의 길이를 150 mm로 하였을 때, 115.7 dB의 평균음압과 630 Hz의 주파수가 나오는 것을 확인하였다.

• 한국세라믹학회지
• /
• 제42권9호
• /
• pp.618-623
• /
• 2005

HTGR (High Temperature Gas-Cooled Reactor) is highlighted to next generation power plant for producing the clean hydrogen gas. In this study, the spherical $UO_2$ kernel via $UO_3$ gel particles was prepared by the sol-gel process. Raw material of slightly Acid Deficient Uranyl Nitrate (ADUN) solution, which has pH = 1.10 and $[NO_3]/[U]$ mole ratio = 1.93, was obtained from dissolution of $U_3O_8$ powder with conc.-$HNO_3$. The surface of these spherical $UO_3$ gel particles, which was prepared from the broth solution, consisted of 1 M-uranium, 1 M-HMTA, and urea, were covered with the fine crystallite aggregates, and these particles were so hard that crushed well. But the other $UO_3$ gel particles prepared with the broth solution, consisted of 2 M-uranium, 2 M-HMTA, and urea, have soft surface characteristics and an amorphous phase. This type of $UO_3$ gel particles is some chance of doing possibility of high density from the compaction. The amorphous $UO_3$ gel particles was converted to $U_3O_8$ and then $UO_2$ by calcination at $600^{\circ}C\;in\;4\%\;-\;H_2\;+\;N2$ atmosphere.

• Journal of Radiation Protection and Research
• /
• 제23권4호
• /
• pp.243-249
• /
• 1998

원자력 사고 후 우유에 대한 비상대응방법론을 비용/편익 분석법에 근거하여 고안하였다. 목초의 왕성한 성장시기인 8월 15일을 방사성물질의 침적시점(사고시점)으로 가정하여 지표위 방사성물질의 농도, 침적 후 대응행위의 시작시점과 수행기간의 함수로써 적용결과를 논의하였다. 침적 후 우유내 방사성물질의 농도는 동적섭식경로모델 DYNACON으로부터 예측되었다 대응행위로는 침적 후 첫해에 피폭을 효과적으로 줄일 수 있고 수행하기 용이한 섭취금지와 비오염 사료대체가 고려되었다. 대응행위 수행에 따른 총비용은 피폭부담과 금전비용의 합으로 평가하였다. 침적 후 신속한 대응은 소요되는 금전비용에 대한 피폭저감 측면에서 중요한 변수였다. 많은 경우 비오염 사료대체는 섭취금지보다 비용측면에서 효과적인 대응행위였다. 대응행위를 빨리 취할수록 대응행위의 정당화 및 최적기간은 증가하였다.

• Corrosion Science and Technology
• /
• 제13권3호
• /
• pp.87-94
• /
• 2014

Recently, the application of bending products has been increased since the industries such as automobile, aerospace, ships, and plants greatly need the usage of pipes. For facility fabrication, bending process is one of key technologies for pipings. Induction heat bending process is composed of bending deformation by repeated local heat and cooling. Because of local heating and compressive strain, detrimental phases may be precipitated and microstructural change can be induced. This work focused on the effect of induction heat bending process on the properties of ASME SA312 TP316 stainless steel. Evaluation was done on the base metal and the bended areas before and after heat treatment. Microstructure analysis, intergranular corrosion test including Huey test, double loop electropotentiokinetic reactivation test, oxalic acid etch test, and anodic polarization test were performed. On the base of microstructural analysis, grain boundaries in bended extrados area were zagged by bending process, but there were no precipitates in grain and grain boundary and the intergranular corrosion rate was similar to that of base metal. However, pitting potentials of bended area were lower than that of the base metal and zagged boundaries was one of the pitting initiation sites. By re-annealing treatment, grain boundary was recovered and pitting potential was similar to that of the base metal.

• 멤브레인
• /
• 제14권3호
• /
• pp.185-191
• /
• 2004

원자력 발전의 고온 가스로(high temperature gas-cooled reactor, HTGR)의 냉각제로 사용되는 He가스의 열에너지를 이용하여 물을 분해해서 수소를 생산하는 "열화학적 수소제조 IS프로세스"에 대해 설명하였다. 특히, 분리막 기술의 이용에 관한 연구를 중점으로 정리하였다. 고온 원자력 열에너지를 이용한 열화학적 수소 제조법은 실현 가능한 단계까지 왔다고 생각되며, 아직 연구 개발 과제가 많이 남아 있지만, 미래의 청정에너지 중의 하나인 수소를 대량 생산할 수 있는 가능성을 갖고 있다.

• Nuclear Engineering and Technology
• /
• 제38권6호
• /
• pp.505-534
• /
• 2006

Ensuring sufficient supplies of clean, economic and acceptable energy is a critical global challenge for the 21st century. There seems little alternative to a greatly expanded role for nuclear power, but implementation of this option will depend on ensuring that all resulting wastes can be disposed of safely. Although there is a consensus on the fundamental feasibility of such disposal by experts in the field, concepts have to be developed to make them more practical to implement and, in particular, more acceptable to key stakeholders. By considering global trends and using illustrative examples from Japan, key areas for future R&D are identified and potential areas where the synergies of international collaboration would be beneficial are highlighted.

• Nuclear Engineering and Technology
• /
• 제44권7호
• /
• pp.767-772
• /
• 2012

In support of optimizing electrorefining technology for treating spent nuclear fuel, lithium drawdown has been investigated for separating actinides from molten salt electrolyte. Drawdown reaction selectivity is a major issue that requires investigation, since the goal is to remove actinides while leaving the fission products and other components in the salt. A series of lithium drawdown tests with surrogate fission product chlorides was run to obtain selectivity data with non-radioactive salts, develop a predictive model, and draw conclusions about the viability of using this process with actinide-loaded salt. Results of tests with CsCl, $LaCl_3$, $CeCl_3$, and $NdCl_3$ are reported here. Equilibrium was typically achieved in less than 10 hours of contact between lithium metal and molten salt under well-stirred conditions. Maintaining low oxygen and water impurity concentrations (<10 ppm) in the atmosphere was observed to be critical to minimize side reactions and maintain stable salt compositions. An equilibrium model has been formulated and fit to the experimental data. Good fits to the data were achieved. Based on analysis and results obtained to date, it is concluded that clean separation between minor actinides and lanthanides will be difficult to achieve using lithium drawdown.

• Nuclear Engineering and Technology
• /
• 제38권4호
• /
• pp.391-398
• /
• 2006

It is recommended to clean steam generators of nuclear power plants during plant outages. Under normal operations, sludge is created and constantly accumulates in the steam generators. The constituents of this sludge are different depending on each power plant characteristics. The sludge of the Kori Unit 1 steam generator, far example, was found to be composed of 93% ferrous oxide, 3% carbon and 1% of silica oxide and nickel oxide each. The research to develop a lancing system that would remove sludge deposits from the tubesheet of a steam generator was started in 1998 by the Korea Electric Power Research Institute (KEPRI) of the Korea Electric Power Corporation (KEPCO). The first commercial domestic lancing system in Korea, the $KALANS^(R)-I$ Lancing System, was completed in 2000 for Kori Unit 1 for cleaning the tubesheet of its Westinghouse Delta-60 steam generator. Thereafter, the success of the development and site implementation of the $KALANS^(R)-I$ lancing system for YGN Units 1&2 and Ulchin Units 3&4 was also realized in 2004 for sludge removal at those sites. The upper bundle cleaning system for Westinghouse model F steam generators is now under development.

• 대한기계학회논문집A
• /
• 제26권8호
• /
• pp.1645-1652
• /
• 2002

The failure analysis on fractured parts is divided into the qualitative method by naked eyes and metallurgical microscope etc. and the quantitative method by SEM and X-ray diffraction etc. X-ray fractography can be applied to contaminated surface as well as clean surface and gain the plastic deformation and the residual stress near the fractured surface. Turbine blade is subject to cyclic bending force by steam pressure and suffers fatigue damage according to the increasing operating time. Therefore, to clean up the fracture mechanism of torsion-mounted blade in nuclear plant, the fatigue and the X-ray diffraction test was performed on the 12%Cr steel fur turbine blade and the fractured parts. The correlation of X-ray parameter and fracture mechanics parameter was determined, and then the load applied to actual broken turbine blade was predicted. Failure analysis was performed by contact stress analysis and Goodman diagram of torsion-mounted blade.

• Corrosion Science and Technology
• /
• 제18권5호
• /
• pp.196-205
• /
• 2019

Surface modification techniques are known to improve SCC by adding large compressive residual stresses to metal surfaces. This surface modification technology is attracting attention because it is an economical and practical technology compared to the maintenance method of existing nuclear power plants. Surface modification techniques include laser, water jet and ultrasonic peening, pinning and ultrasonic Nano-crystal surface modification (UNSM). The focus of this study was on the effect of ultrasonic amplitude in UNSM treatment on the corrosion properties of Alloy 600. A microstructure analysis was conducted using an optical microscope (OM), scanning electron microscope (SEM) and electron backscattering diffraction (EBSD). A cyclic polarization test and AC-impedance measurement were both used to analyze the corrosion properties. UNSM treatment influences the corrosion resistance of Alloy 600 depending on its amplitude. Below the critical amplitude value, the pitting corrosion properties are improved by grain refinement and compressive residual stress, but above the critical amplitude value, crevices are formed by the formation of overlapped waves. These crevices act as corrosion initiators, reducing pitting corrosion resistance.