• Title/Summary/Keyword: nuclear pore

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N-Acetyl-D-Glucosamine Kinase Is a Component of Nuclear Speckles and Paraspeckles

  • Sharif, Syeda Ridita;Lee, HyunSook;Islam, Md. Ariful;Seog, Dae-Hyun;Moon, Il Soo
    • Molecules and Cells
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    • v.38 no.5
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    • pp.402-408
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    • 2015
  • Protein O-GlcNAcylation, dictated by cellular UDP-N-acetylglucosamine (UDP-GlcNAc) levels, plays a crucial role in posttranslational modifications. The enzyme GlcNAc kinase (NAGK, E.C. 2.7.1.59) catalyzes the formation of GlcNAc-6-phosphate, which is a major substrate for the biosynthesis of UDP-GlcNAc. Recent studies have revealed the expression of NAGK in different types of cells especially in neuronal dendrites. Here, by immunocytochemistry (ICC) and immunonucleochemistry (INC) of cultured rat hippocampal neurons, HEK293T and GT1-7 cells, we have showed that NAGK immuno-reactive punctae being present in the nucleoplasm colocalized with small nuclear ribonucleoprotein-associated protein N (snRNPN) and p54NRB, which are speckle and paraspeckle markers, respectively. Furthermore, NAGK IR cluster was also found to be colocalized with GTF2H5 (general transcription factor IIH, polypeptide 5) immuno reactive punctae. In addition, relative localization to the ring of nuclear lamin matrix and to GlcNAc, which is highly enriched in nuclear pore complexes, showed that NAGK surrounds the nucleus at the cytoplasmic face of the nuclear outer membrane. By in situ proximity ligation assay (PLA) we confirmed the colocalization of NAGK with snRNPN in the nucleus and in dendrites, while we also verified the interactions of NAGK with p54NRB, and with GTF2H5 in the nucleus. These associations between NAGK with speckle, paraspeckle and general transcription factor suggest its regulatory roles in gene expression.

The Comparison of Sintering Characteristics between the PVA-Al(III) Complex added $UO_2$Pellet and AlOOH added $UO_2$pellet (PVA-Al(III) 착물 첨가 $UO_2$소결체와 AlOOH 첨가 $UO_2$소결체의 소결 특성 비교)

  • Lee, Sin-Yeong;Yu, Ho-Sik;Lee, Seung-Jae;Kim, Hyeong-Su;Bae, Gi-Gwang
    • Korean Journal of Materials Research
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    • v.10 no.1
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    • pp.55-61
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    • 2000
  • The sintering characteristics of PVA-Al(III) complex added $UO_2$ pellet and AlOOH added $UO_2$pellet were compared. The major phase of PVA-Al(III) complex and AlOOH decomposed at $1000^{\circ}C$ in $H_2$atmosphere was $\theta-Al_2O_3$. Compared with the apparent density of pure $UO_2$, that of AlOOH added $UO_2$ powder was higher but that of PVA-Al(III) complex was lower. the densification of AlOOH added $UO_2$ pellet was initiated at about $800^{\circ}C$, the densification of PVA-Al(III) complex added $UO_2$ pellet was initiated at about $900^{\circ}C$ respectively. In a view of pore size distribution, the PVA-Al(III) complex added $UO_2$ pellet appeared as monomodal type, whereas the AlOOH added $UO_2$ pellet appeared as bimodal type. The grain size of AlOOH added $UO_2$ pellet was about $13\mu\textrm{m}$ but the grain size of PVA-Al(III) complex added $UO_2$ pellet was increased up to about $36\mu\textrm{m}$.

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Determination of Uranium Isotopes in Spent Nuclear Fuels by Isotope Dilution Mass Spectrometry (동위원소희석 질량분석법을 이용한 사용후핵연료 중 우라늄 동위원소 정량)

  • Kim, Jung Suk;Jeon, Young Shin;Son, Se Chul;Park, Soon Dal;Kim, Jong Goo;Kim, Won Ho
    • Analytical Science and Technology
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    • v.16 no.6
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    • pp.450-457
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    • 2003
  • The determination of uranium and its isotopes in spent nuclear fuels by isotope dilution mass spectrometry (IDMS) has been studied. The spent fuel samples were dissolved in 8 M $HNO_3$ or its mixture with 14 M $HNO_3-0.05M$ HF. The dissolved solutions were filterred on membrane filter with $1.2{\mu}m$ pore size. The uraniums in the spiked and unspiked sample solutions were quantitatively adsorbed by anion exchange resin, AG 1X8 and eluted with 0.1 M HCl. The contents of uranium and its isotopes ($^{234}U$, $^{235}U$, $^{236}U$$^{238}U$) in the spent fuel samples were determined by isotope dilution mass spectrometric method using $^{233}U$ as spike. The spike reference solution was standarized by reverse isotope dilution mass spectrometry (R-IDMS) using natural and depleted uranium. The results from IDMS were in average relative difference of 0.34% when compared with those by the potentiometric titration method.

A Mechanistic Model for In-Reactor Densification of U$O_2$ (U$O_2$ 핵연료의 노내 기계론적 고밀화 모형)

  • Woan Hwang;Keum Seok Seo;Ho Chun Suk
    • Nuclear Engineering and Technology
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    • v.17 no.2
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    • pp.116-128
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    • 1985
  • Considering vacancy generation and migration in grain and sink at grain boundary, a mechanistic densification model which is dependent on UO$_2$ temperature and microstructure has been developed. This densification model is a function of time, fission rate, temperature, density, pore size distribution and grain size. The resultant equation derived in this model which is different from Assmann and Stehle's resultant equations for four temperature regions, can be applied directly for all the pellet temperatures. The predictions of the present densification model very well agreed with the experimental data. This model well predicts absolute magnitude and trend in comparison with the empirical algorithm used in KFEDA code.

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Effect of Post-heat Treatment on Fatigue Strength of Thermally-Sprayed Stellite Alloy on Steel (스텔라이트 합금 용사 코팅의 피로 강도에 미치는 후열처리의 영향)

  • Oh Jeong Seong;Komotori Jun;Rhee Chang Kyu
    • Journal of Powder Materials
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    • v.12 no.2 s.49
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    • pp.106-111
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    • 2005
  • The effect of post-heat treatment on the coating characteristics and the fatigue strength of the gas flame thermally sprayed Stellite alloy coatings on $0.35\%$ carbon steel were investigated. The fatigue fracture surfaces of the heat treated samples were observed using SEM (Scanning Electron Microscopy). For as-sprayed samples, there was considerable scattering in the fatigue life due to the presence of the pores in the coating. After the post-heat treatment to improve the microstructural characteristics of the coating layer, the fatigue strength of the specimens was greatly improved, increasing with increasing the coating thickness. For the specimens with the 0.3mm and 0.5mm thick coating, the fatigue cracks originated in the substrate region just below the interface. On the contrary, for the specimens with the 1.0mm thick coating, they nucleated at the pore within the coating, and the fatigue strength was 2.6 times higher than that of the substrate due to the high fatigue resistance of the coating.

Effects of the Decomposition Residue of Compound Additive on Resintering Behavior

  • Kim, H.S.;C.Y. Joung;Kim, S.H.;S.H. Na;Lee, Y.W.;D.S. Sohn
    • Nuclear Engineering and Technology
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    • v.34 no.4
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    • pp.323-330
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    • 2002
  • Various types of compounds were tested with the aspects of decomposition and formation of residue in a $CO_2$ or 7H$_2$+93$N_2$ atmosphere. The evaporation temperature range of each compound was determined from thermogravimetric curve. Decomposition of dicarbon amide, stearic acid, acrowax and zinc stearate was studied by thermogravimetry in $CO_2$ or in 7H$_2$+93$N_2$ atmosphere. All compounds were decomposed in $CO_2$ atmosphere at lower than 40$0^{\circ}C$, but the residue, ZnO remained for zinc stearate. ZnO did not decompose in $CO_2$ atmosphere up to 130$0^{\circ}C$, but reduced into Zn metal and disappeared in the temperature range of $600^{\circ}C$ to 120$0^{\circ}C$ in 7H$_2$+93$N_2$ atmosphere. The effect of residue, which trapped in closed pores of sintered pellet, on the thermal stability was studied using the resintering test at 1$700^{\circ}C$ in 7H$_2$+93$N_2$ atmosphere. In the case of oxidative sintered pellet with admixing zinc stearate, the cavity formation accompanied with a density drop after resintering is due to the pressure of the Zn gases trapped in the isolated pores.

Experimental study of sodium fire and its characteristics under the coupling action of columnar liquid sodium flow and concrete

  • Huo, Yan;Zou, Gao-Wan;Dong, Hui;Lv, Jian-Fu;He, Jian
    • Nuclear Engineering and Technology
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    • v.53 no.9
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    • pp.2866-2877
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    • 2021
  • The complex coupling relationship between liquid sodium and concrete materials affects both the sodium fire characteristics and concrete properties through heat and chemical erosion. In this study, experiments on direct and indirect (separated by a steel plate) contact of the columnar sodium fire with the concrete surface were performed. It was found that the combustion efficiency of liquid sodium in direct contact with concrete was significantly enhanced and accompanied by intermittent explosions and splashing of small concrete fragments. The sodium fire on the surface of the concrete considerably increased the internal temperature, pore size, and distribution density of the concrete. In addition, the depth of influence on the loosening of the concrete structure was also greatly extended. The contact of liquid sodium with the concrete substantially affected its permeability resistance. The water absorption of the concrete surface was increased by more than 70% when liquid sodium directly impacted the bare concrete surface. However, the change in water absorption in the centre of the concrete was primarily affected by the duration of the external heat.

Adsorption and Desorption Characteristics of Fission Molybdenum on Alumina (알루미나에 의한 Fission 몰리브덴의 흡착과 탈착 특성)

  • 조경태;정원명;이종대
    • Journal of the Korean Society of Safety
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    • v.12 no.3
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    • pp.97-105
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    • 1997
  • Mo-99(Molybdenum) is the only source of Tc-99m(Technetium) which is most frequently used in nuclear medical diagnostics and the demand is on the increase recently. Separation and refining of Mo-99 was investigated by adsorption and desorption on alumina. At pH=0.63, adsorption isotherm of Mo was fitted by Redlich & Peterson equation using the adsorption experimental data. It was found that the pore diffusion model ($D_p=1.4{\times}10^{-6}cm^2/s, K_f/=0.4 cm/s$) agreed well with batch adsorption experimental data. RTDs(Residence Time Distributions ) were measured and axial dispersion coefficients were obtained in the fixed bed absorber according to the changes of the flow rate using 0.05% -NaCl. From the adsorption experimental data, it was shown that the behavior of breakthroughs depended on flow rate. Mo recovery yield was increased as adsorption flow rate was increased and desorption flow rate was decreased.

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Separation and Purification of Useful Proteins Using Hydrogel Ultratiltration

  • Park, Chang-Ho;Son, Chang-Kyu;Park, Jong-Hwa;Chung, In-Sik
    • Biotechnology and Bioprocess Engineering:BBE
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    • v.2 no.2
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    • pp.113-116
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    • 1997
  • The hydrogel process is a different form of ultrafiltration and has been used to separate biological molecules. In this study, the gel pore size was predicted by pulse NMR technique and neural network using a database obtained from gel filtration chromatography and diffusion experiment. Recombinant alkaline phosphatase expressed in insect cells was concentratred 1.5 times by hydrogel ultrafiltration by swelling at 2$0^{\circ}C$ and collapsing at 35$^{\circ}C$ at 53-65% separation efficiency and 78-83% enzyme recovery. Wild and recombinant Autographa californica unclear polyhedrosis viruses (AcNPV) were also concentrated 1.4 and 1.6 times of the feed solution at 48.5 and 60.0% separation efficiency, respectively Hydrogel ultrafiltration appears to be an attractive alternative for the concentration of AcNPV and recombinant proteins from insect cells.

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Modeling of the Time-Dependent Changes of Micro Pore Structures in Concrete for Nuclear Power Plants (원전콘크리트의 미세공극구조 경시변화 예측 모델 개발)

  • Kim, Joo-Hyung;Jung, Sang-Hwa;Moon, Jae-Heum
    • Proceedings of the Computational Structural Engineering Institute Conference
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    • 2010.04a
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    • pp.762-765
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    • 2010
  • 본 연구에서는 원전격납구조물과 같이 고품질을 요하는 콘크리트의 내구성설계 및 관리에 필요한 구조물 건전성 평가시스템 구축의 일환으로 콘크리트 미세공극구조 형성 예측 프로그램을 개발하였다. 개발된 미세공극구조 형성 예측 프로그램은 콘크리트의 강도 등과 같은 역학적 특성 및 유해이온 확산거동 예측에 활용되는 부분으로서 기존의 연구결과로부터 개발된 모델식들을 바탕으로 개발되었다. 개발된 프로그램은 콘크리트 시험체로부터 구하여진 MIP 실험결과와 비교해 보았으며, 상관성을 검토하였다.

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