• Defense and Technology
• /
• no.9 s.163
• /
• pp.46-50
• /
• 1992

고온, 고압의 추진제 연소가스로부터 노즐 구조물을 보호하기 위해 사용되는 열 차폐용 삭마성 내열재료(ablative material)의 종류와 재료선정을 위한 시험방법, 설계 및 제작기법, 성능평가 기준 등에 관한 연구동향을 검토하고 본 연구팀의 연구결과를 제시하였습니다 고체추진제 연소 환경하에서의 노즐 보호재료로서는 고분자계 삭마성 내열재가 주로 사용되는데, 이 ablative material에는 여러 종류가 있으나 높은 heat flux와 빠른 mass flow에 대한 내열을 위해서는 페놀, 폴리이미드 등 열경화성 수지인 charring material이 모재로 주로 사용되며 강도향상을 위해서 탄소, 실리카, 석면, 유리등의 강화섬유가 보강재로 사용됩니다 현재는 모재로서 고분자계 수지외에도 세라믹과 같은 무기재료, 금속재료등과 강화섬유를 조합하여 내열성과 강도가 향상된 재료를 개발하는 연구도 진행되고 있습니다

• Proceedings of the Korean Nuclear Society Conference
• /
• 1996.11b
• /
• pp.769-774
• /
• 1996

DUPIC 공정은 재처리공정과는 달리 공정의 전ㆍ후를 통하여 사용후핵연료의 양이 변하지 않기 때문에 시설이 원활히 운전되기 위해서는 사용후핵연료가 결손 또는 전용되지 않았음을 증명할 수 있어야 한다. 따라서, 핵투명성(nuclear transparency)을 보장할 수 있는 DUPIC 핵연료 보장조치용 비파괴측정 장치의 개발이 요구되었으며 $^3$He tube, 폴리에칠렌(CH$_2$)감속재, 텅스텐 차폐체 그리고 PSR(portable shift register) 등으로 구성된 측정 시스템을 제작하였다. 본 장치를 사용하여 사용후핵연료에서 검출되는 중성자중에서, $^{244}$ Cm의 자발핵분열중성자 수를 분석할 수 있으며 이를 이용하여 사용후핵연료를 계량관리 할 수 있다. 현재 측정시스템에 대한 성능시험등을 수행하고 있는 중이며 향후 DUPIC 연구용 고준위방사성물질취급시설(hot-cell)에 설치할 예정이다.

• Composites Research
• /
• v.15 no.2
• /
• pp.18-23
• /
• 2002

The absorption and the interference shielding of the problems thor both commercial and military purposes. In this study, the minimization of the electromagnetic wale reflections using composite layers with different dielectric properties was performed. Dielectric constants were measured for glass/epoxy composites containing conductive carbon blacks and carbon/epoxy fabric composites. Using the measured permittivities of the composites having various carbon black contents, the optimal electromagnetic wave absorbing structure in X-band(8.2GHz-12.4GHz) was determined. The optimal multi-layered composite plates have the thickness of 2.6mm. The maximum reflection loss is -30dB at 10GHz, and the bandwidth haying the absorptivity lower than -l0dB is about 2GHz.

• Progress in Medical Physics
• /
• v.9 no.3
• /
• pp.137-141
• /
• 1998

The purposes of this report are to evaluate whether lead ball and steel ball could be used as protective material of radiation and to acquire physical data of them for protecting 4-10 MV X-ray beams. Lead balls of diameter 2.0～2.5mm or steel balls of diameter 1.5～2.0 mm were filled in an acrylic box of uniform width. An MV radiograph of metal balls in a box were taken to ascertain uniformity of ball distribution in the box. Average density of metal ball and linear attenuation coefficient of metal balls for 4～10 MV X -rays were measured. At the time of measurement of linear attenuation coefficient, Farmer ionization chamber was used and to minimize the scatter effect, distance between the ball and the ionization chamber was 70 cm and field size was 5.5cm${\times}$5.5cm. For comparison, same parameters of lead and steel plates were measured. The distribution of metal balls was uniform in the box. The density of a mixture of lead-air was 6.93g/cm$^3$, 0.611 times density of lead, and the density of a mixture of steel-air was 4.75g/cm$^3$, 0.604 times density of steel. Half-value layers of a mixture of lead-air were 1.89 cm for 4 MV X-ray, 2.07 cm for 6 MV X-ray and 2.16 cm for 10 MV X-ray, and approximately 1.64 times of HVL of lead plate. Half-value layers of a mixture of steel-air were 3.24 cm for 4 MV X-ray, 3.70 cm for 6 MV X-ray and 4.15 cm for 10 MV X-ray, and approximately 1.65 times of HVL of lead plate. Metal balls can be used because they could be distributed evenly. Average densities of mixtures of lead-air and steel-air were 6.93g/cm$^3$, 4.75g/cm$^3$ respectively and approximately 1.65 times of densities of lead and steel. Product of density and HVL for a mixture of metal-air are same as the metal.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
• /
• v.5 no.3
• /
• pp.199-212
• /
• 2007

If a type IP-2 transport package were to be subjected to a free drop test and a penetration test under the normal conditions of transport, it should prevent a loss or dispersal of the radioactive contents and a more than 20% increase in the maximum radiation level at any external surface of the package. In this paper, we suggested the analytic method to evaluate the structural safety of a type IP-2 transport package using a thick steel plate for a structure part and a bolt for tying a bolt. Using an analysis a loss or dispersal of the radioactive contents and a loss of shielding integrity were confirmed for two kinds of type IP-2 transport packages to transport radioactive waste drums from a waste facility to a temporary storage site in a nuclear power plant. Under the free drop condition the maximum average stress at the bolts and the maximum opening displacement of a lid were compared with the tensile stress of a bolt and the steps in a lid, which were made to avoid a streaming radiation in the shielding path, to evaluate a loss or dispersal of radioactive waste contents. Also a loss of shielding integrity was evaluated using the maximum decrease in a shielding thickness. To verify the impact dynamic analysis for free drop test condition and evaluate experimentally the safety of two kinds of type IP-2 transport packages, free drop tests were conducted with various drop directions. For the tests we examined the failure of bolts and the deformation of flange to evaluate a loss or dispersal of radioactive material and measured the shielding thickness using a ultrasonic thickness gauge to assess a loss of shielding integrity. The strains and accelerations acquired from tests were compared with those by analyses to verify the impact dynamic analysis. The analytic results were larger than the those of test so that the analysis showed the conservative results. Finally, we evaluated the safety of the type IP-2 transport package under the stacking test condition using a finite element analysis. Under the stacking test condition, the maximum Tresca stress of the shielding material was 1/3 of the yielding stress. Two kinds of a type IP-2 transport package were safe for the free drop test condition and the stacking test condition.

• Composites Research
• /
• v.17 no.3
• /
• pp.38-44
• /
• 2004

The electromagnetic interference (EMI) shielding is very essential for commercial and military purposes. We fabricated multi-walled carbon nanotube (MWNT)/epoxy composites and studied the electromagnetic characteristics of the composites before we study the characteristics of MWNT-added glass fiber-reinforced composites. After setting up the fabrication process, we measured the permittivity of MWNT/epoxy composites with process variables and MWNT concentrations in X-band (8.2GHz~12.4GHz). We also observed re-aggregation phenomenon of MWNTs and investigated its effect on the permittivity. The permittivity of the composites was influenced by the degree of dispersion of MWNTs and increased almost linearly as MWNT concentration increases.

• Composites Research
• /
• v.31 no.3
• /
• pp.111-116
• /
• 2018

In this paper, magnetic FeCoNi particles have been grown through electroless plating on the surface of graphene, and then this hybrid material has been dispersed by various surfactants to prepare films. The pyridine surfactant shows the highest dispersability and low surface resistance value (351 Ohm/sq) and the electromagnetic shielding ability at the frequency of 10 GHz. Specially, the evaporation of the pyridine during the drying process could be able to form the internal conductive network and high dispersion of FeCoNi on the surface of graphene.

• Journal of Soil and Groundwater Environment
• /
• v.16 no.4
• /
• pp.53-61
• /
• 2011

This study examined evaluation on stabilization of major and trace elements in tailings by various surface water-preventing materials. Six columns were filled with tailings of the Sinlim mine, then covered with tailings only, compacted soils, clay, soil-bentonite mixture, pozzolan and bentonite mat. After injection of artificial rain water, the leachate was sampled with times (3, 6, 9 and 12 pore volume) and analysed for major (Ca, Na, Mg, K) and trace elements (As, Cd, Cu, Pb, Zn) by ICP-AES. With exception to pozzolan type, the pH values of leachate from the other types became stabilized from 5.5 to 7.5, and EC (electric conductivity) of leachate from them decreased with times. For the pozzolan type, however, the pH and EC of leachate increased with time due to its alkalinity producing system. Concentrations of most major and trace elements in leachate decreased and stabilized with time. Consequently, soil-bentonite mixed cover shows the best ability of water-preventing and reducing mobility of elements in tailings site.

• 한국신재생에너지학회:학술대회논문집
• /
• 2011.05a
• /
• pp.108-108
• /
• 2011

공동주택에서 2025년 정부가 추진하고 있는 Zero Energy 건축물 구현과 친환경에 대한 탄소배출 저감 문제로 재생에너지 생산시스템의 추가 적용은 반드시 필요하다. 따라서 공동주택 적용 및 활용성을 높일 수 있는 BIPV시스템 개발을 통하여 설치면적 확보와 세대 활용성을 높일 수 있도록 하는 것이 필요하다. 특히 거실 창호의 경우 주방향이 남향, 남동 또는 남서향으로 배치되어 태양광을 적용하기에 적합한 특성을 가지고 있다. 그러나 창호는 건물외피의 역할과 재실자가 조망과 정보취득을 얻을 수 있는 중요한 통로가 되기 때문에 단열 문제나 시야 차폐의 문제는 발생하지는 않도록 하는 것이 필요하다. 본 연구에서는 a-si타입 모듈 2개를 10% 투과율로 Bsck Coating 색상을 달리한 모듈과 c-si BIPV 모듈을 커튼월 창호시스템으로 개발, 일반 2중 창호시스템과 비교 평가를 위해 실제 Test bed 건물에 시공하여 시환경 및 실내 창측면 온도변화 측정 분석을 진행하였다. 현재 국내외 출시되고 있는 a-si see through 모듈은 10~30%의 투과율로 창 마감재로 대체가 가능하나 건축 환경(시환경,열환경)에 대한 분석은 전무한 상태이다. 본 연구에서는 시환경과 창유리면의 열 부하, 자외선, 적외선 차폐 및 가시광선의 투과율에 대한 평가와 Back Coating에 따른 색온도 평가를 통해서 a-si BIPV의 공동주택 세대 발코니 창호 적합성에 대한 검토를 진행하였다. 연구결과는 아래와 같다. ${\bullet}$ 실내조도는 청천공 정오기준 가시성 확보 모듈의 경우 2,300 ~ 3,500lx를 나타내고 있어 대비 현상이나 창측의 급격한 조도 변화가 적은 시환경 구축이 가능 ${\bullet}$ 12시경 휘도는 창측면, 실내 벽체, 코너 바닥면을 대상으로 a-si BIPV 모듈을 적용한 경우 휘도비가 12:1로 KS나 IESNA의 광원과 근접면의 비 20:1 범위에 모두 존재, 적합한 것으로 분석되었으나 c-si의 경우는 그림자로 인한 대비 현상이 발생, 작업 시환경 문제 발생. ${\bullet}$ 이중시스템 창호와 비교하여 단열 성능 떨어짐. 발전시간대 창유리 면 온도 상승 으로 하절기 냉방부하 증가. ${\bullet}$ 자외선은 100% 가까이 차단, 적외선은 13~42%만 투과되고 가시광선은 13% 투과율을 나타내어 일반 창에 칼라 코팅을 적용하는 것과 유사한 경향을 나타냄.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
• /
• v.6 no.3
• /
• pp.233-244
• /
• 2008

A conceptual design study for a pyroprocesing facility, has been carried out in this study, which is available for the recovery of uranium and transuranic elemental group(TRU), that is, reusable as a nuclear fuel especially in a next generation-type reactor. The scale of this facility has been chosen as 20 kg HM/batch, comparatively small engineering size in order to collect scale-up data for the design of a commercial facility as well as to get operational experience. The spent fuel to be handled in this process is as follows : 3.5 % enriched uranium fuel, 35,000MWd/tU and 5-year cooled. The major items considered in the conceptual study are a building lay-out including various hot cells, safety management of the process operation in conjunction with material balance control, radiation safety, inert atmosphere control in shielded hot cells, and criticality control of uranium and TRU products.