• BMB Reports
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• 제42권1호
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• pp.22-27
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• 2009

Replication Protein A (RPA) is a single stranded DNA-binding protein involved in DNA metabolic activities such as replication, repair, and recombination. RPA-Interacting Protein $\alpha$ ($RIP{\alpha}$) was originally identified as a nuclear transporter of RPA in Xenopus. The human $RIP{\alpha}$ gene encodes several splice isoforms, of which $hRIP{\alpha}$ and $hRIP{\beta}$ are the major translation products in vivo. However, limited information is available about the alternative splicing of $RIP{\alpha}$ in eukaryotes, apart from that in humans. In this study, we examined the alternative splicing of RIP{\alpha} in the Drosophila, Xenopus, and mouse system. We showed that the number of splice isoforms of RIP{\alpha} was species-specific, and displayed a tendency to increase in higher eukaryotes. Moreover, a mouse ortholog of $hRIP{\alpha}$, $mRIP{\beta}2$, was not SUMOylated, in contrast to $hRIP{\alpha}$. Based on these results, we suggest that the $RIP{\alpha}$ gene gains more splice isoforms and additional modifications after molecular evolution.

• Nuclear Engineering and Technology
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• 제41권1호
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• pp.135-142
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• 2009

In this investigation, we prepared a 1 and 3-parallel serpentine single PEMFC, which has an active area of $100\;cm^2$ and a flow channel cross section of $1{\times}1mm$. Distribution and transport of water in a non-operating PEMFC were observed by varying flow types and the flow rates (250, 400, and 850 cc/min). This investigation was performed at the neutron imaging facility at the CO1d Neutron RAdiography facility (CONRAD), HMI, Germany of which the collimation ratio and neutron fluence rate are 250, $1{\times}10^{6}n/s/cm^2$, respectively. The neutron image was continuously recorded by a scintillator and lens-CCD coupled detector system every 10 seconds. It has been observed that although the distilled water was supplied into the cathode channel only, the neutron image showed a water movement from the cathode to the anode channel. The water at the cathode channel was completely discharged as soon as the pressurized air was supplied. But the water at the anode channel was not easily removed by the pressurized air except for the 3-parallel serpentine type with 850cc/min of air flow rate. Moreover, the water at the MEA wasn't removed for any of the cases.

• 한국안광학회지
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• 제12권4호
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• pp.133-139
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• 2007

Calretinin의 생리적 역할은 아직 확립되지 않았지만, 칼슘 buffer로서의 작용과 칼슘 중재의 신호 변환에 적극적으로 작용하고 있다. Calretinin은 인간의 망막에서 성체 광수용체 세포와 이극세포, 수평세포에서 칼슘의 수송과 칼슘의 생리적 buffering으로서의 역할을 하고 있다. 본 연구에서 한국관 박쥐의 망막의 내핵층과 신경절세포층에서 calretinin의 면역세포화학반응 신경세포들과 그 분포 양상을 조사하여 우리는 박쥐 망막에서 calretinin에 면역세포화학반응을 일으키는 AII 무축삭세포를 내핵층에서 그리고 신경절세포층에서는 신경절세포들을 확인할 수 있었다. 이번의 관찰연구는 우리의 이전 연구와 더불어 박쥐 시력의 풀리지 않는 문제와 박쥐비행의 기동성의 독특한 행동적인 측면들을 더욱 많이 이해하는데 필요하다고 생각한다.

• 방사성폐기물학회지
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• 제10권4호
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• pp.255-262
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• 2012

원전이 위치한 동해 월성 연안역 주변에서 오염물 이동 확산에 대한 수치 모사를 수행하였다. 월성 연안역의 유속장 재현을 위한 해수유동 수치모형 실험은 EFDC(Environmental Fluid Dynamics Code) 모델을 사용하여 조위 시계열 검증 및 조화분석을 통한 검증을 실시한 결과 양호한 재현성을 나타내었다. 월성 주변해역의 유속장 산정 결과 창조류시에는 남향, 낙조류 시에는 북향으로 진행되는 결과를 알 수 있었다. 또한 국립수산과학원에서 관측한 수온, 염분의 자료를 이용하여 수치모델을 통한 계산값과 관측값을 비교한 결과 양호한 재현성을 나타내었다. 계산된 해수유동자료와 수온, 염분의 결과를 이용하여 오염물질의 확산특성을 해석하였다.

• 대한핵의학회지
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• 제28권1호
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• pp.112-123
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• 1994

${\gamma}$-Glutamyltransferase (GGT: E.C. 2.3.2.2.) is a glycoprotein enzyme which is involved in glutathione metabolism and amino acid transport through the plasma membrane. It is distributed widely in several organs including liver and kidney. Several isozymes of GGT have been reported and some of the isozymes may be associated with hepatocarcinogenesis. We have produced six monoclnal antibodies (mAbs) against GGT purified from the liver of 2-acetamidofluorene (AAF) treated rats. All of the six mAbs were obtained by immunizing mice with liver GGT Six hybridomas which produced anti-GGT Abs were extensively subcloned and injected into the peritoneal cavity of BALB/c mice to obtain large quantities of Abs. These mAbs were purified from ascites by ammonium sulfate precipitation and protein A sepharose CL-4B column chromatography. Using these mAbs we preformed enzyme-linked immunosorbent assay (ELISA), radioimmunoassay (RIA), immunohistochemistry (IHC), and autoradiography (ARG) to study the distribution of GGT isozyme in tissue. The results indicate that GGT-mAb 1 is specific for the AAF treated liver GGT, GGT-mAb 5 for the normal liver GGT, and GGT-mAb 6 for the normal kindey GGT. These mAbs may be used to evaluate the distribution of GGT isozymes in different tissues.

• Nuclear Engineering and Technology
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• 제47권5호
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• pp.523-533
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• 2015

Three-dimensional flow phenomena in a wire-wrapped 37-pin fuel assembly mock-up of a Japanese loop-type sodium-cooled fast reactor, Monju, were investigated with a numerical analysis using a general-purpose commercial computational fluid dynamics code, CFX. Complicated and vortical flow phenomena in the wire-wrapped 37-pin fuel assembly were captured by a Reynolds-averaged Navier-Stokes flow simulation using a shear stress transport turbulence model. The main purpose of the current study is to understand the three-dimensional complex flow phenomena in a wire-wrapped fuel assembly to support the license issue for the core design. Computational fluid dynamics results show good agreement with friction factor correlation models. The secondary flow in the corner and edge subchannels is much stronger than that in an interior subchannel. The axial velocity averaged in the corner and edge subchannels is higher than that averaged in the interior subchannels. Three-dimensional multiscale vortex structures start to be formed by an interaction between secondary flows around each wire-wrapped pin. Behavior of the large-scale vortex structures in the corner and edge subchannels is closely related to the relative position between the hexagonal duct wall and the helically wrapped wire spacer. The small-scale vortex is axially developed in the interior subchannels. Furthermore, a driving force on each wire spacer surface is closely related to the relative position between the hexagonal duct wall and the wire spacer.

• Corrosion Science and Technology
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• 제15권2호
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• pp.84-91
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• 2016

The transport and deposition of corrosion products in pressurized water nuclear reactor (PWR) steam generators have led to corrosion (SCC, denting etc.) problems. Lancing, mechanical cleaning and chemical cleaning have been used to reduce these problems. The methods of lancing and mechanical cleaning have limitations in removing corrosion products due to the structure of steam generator tubes. But high temperature chemical cleaning (HTCC) with EDTA is the most effective method to remove corrosion products regardless of the structure. However, EDTA in chemical cleaning aqueous solution and chemical cleaning environments affects the integrity of materials used in steam generators. The nuclear power plants have to perform the pre-test (also called as qualification test (QT)) that confirms the effect on the integrity of materials after HTCC. This is one of the series studies that assess the effect, and this study determines the effects of 20 % EDTA aqueous solution on defective tubes in high temperature chemical cleaning environments. The depth and magnitude of defects in steam generator (SG) tubes were measured by eddy current test (ECT) signals. Surface analysis and magnitude of defects were performed by using SEM/EDS. Corrosion rate was assessed by weight loss of specimens. The ECT signals (potential and depth %) of defective tubes increased marginally. But the lengths of defects, oxides on the surface and weights of specimens did not change. The average corrosion rate of standard corrosion specimens was negligible. But the surfaces on specimens showed traces of etching. The depth of etching showed a range on the nanometer. After comprehensive evaluation of all the results, it is concluded that 20 % EDTA aqueous solution in high temperature chemical cleaning environments does not have a negative effect on defective tubes.

• Journal of Radiation Protection and Research
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• 제18권2호
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• pp.47-59
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• 1993

본 연구에서는 사용후핵 연료를 안전하게 수송할 수 있는 수송용기의 여러 가지 설계 항목중에 수송용기 내부에 장전한 핵연료에 의한 핵임계반응을 방지하기 위한 핵임계해석을 수행하였다. 핵임계 해석에 사용한 HANSEN-ROACH-KENO-Va 전산시스템에 대한 검증계산을 수행하였고 수송용기의 핵임계측면에서의 안전성을 확보하기 위해 가능한 보수적인 가정을 하여 어떠한 경우에도 수송용기에 장전된 핵연료가 임계상태에 도달하지 않도록 수송용기 내부의 구조 및 적절한 핵임계 방지제를 선택하였고 정상수송 및 가상사고 조건 등에 대한 해석을 수행하였다. 그 결과 KSC-7 수송용기 의 설계조건을 만족하고 핵임계측면에서의 안전성을 보장할 수 있는 재료 및 구조에 대한 결론을 해석적으로 도출하였다.

• Journal of Radiation Protection and Research
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• 제29권3호
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• pp.157-163
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• 2004

원자력시설에서 만일의 방사성 물질의 누출이나 화학시설에서 독성물질의 누출시 오염물질의 환경 중 거동을 파악하기 위해서 대기확산 모형이 많이 이용된다. 대기확산 모형을 통한 환경 중 유해물질의 농도 예측에 대한 정확도를 높이기 위해서는 무엇보다 모형으로 입력되는 선원항에 대한 정확한 정보를 필요로 한다. 본 연구는 이러한 선원항 추정을 위하여 최소자승법을 적용하였다. 영광원자력 시설에서 실시된 추적자 확산실험 자료를 이용하여 가우시안 모형으로 계산한 값과 비교를 시도하였으며, 가우시안 모형으로 계산한 값들과 추적자 확산실험 결과 값들의 오차의 제곱이 최소가 되도록 선원항을 추정하였다. 추정한 선원항은 확산실험시 실제추적자 방출량의 1.24정도로 비교적 정확한 예측력을 나타내었다.

• Nuclear Engineering and Technology
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• 제20권2호
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• pp.120-131
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• 1988

지중매몰된 방사성핵종들이 지하수계를 통해 이동을 하는 Source를 수학적으로 표시하는 Source Term 모형이 필요하다. 물질전달식 또는 측정식에 근거한 여러 Source Term 모형을 비교 분석하였다. 일반적으로 용출 또는 용해에는 (1) 화학반응, (2) 확산 등에 의한 물질이동의 두 가지 작용이 관여한다. 화학반응은 고화체가 지하수에 노출된 후 초기의 짧은 기간 동안에만 용해율을 조절한다. 외부로의 물질전달율이 지하 처분장에서 방사성폐기물 고화체로부터의 장기간에 걸친 핵종유출율을 조절하는 역할을 한다. 물질전단 이론을 적용 할 때는, 필요로 하는 물질이동 현상을 기술할 수 있는 식을 선택해야 한다. 적절히 사용했을 경우, 물질전달 이론에 입각한 Source Term 모형은 핵종유출율의 신뢰할 만한 예측을 위한 귀중한 도구이다.