• 대한한약학회:학술대회논문집
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• 대한한약학회 2007년도 Autumn Conference
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• pp.187-188
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• 2007

• Applied Microscopy
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• 제30권4호
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• pp.403-412
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• 2000

1. 아메바 항-액틴의 Ag-Ab 반응과 이를 항-생쥐 IgG-금 입자로 표지한 결과는 주로 정세 포 및 정자의 핵질에 특이적으로 표지되었고 첨체에서는 그 반응을 볼 수 없었다. 2. 표지된 항-액탠 금 입자로 볼 때 정자 핵질의 G-액틴 또는 G-actin oligomer는 정세포의 F-액틴에서 유래되는 것으로 사료된다. 3. 첨체의 액틴은 주로 F-액틴으로 첨체돌기 형성에 참여하지 않는 위상인 것으로 관찰된다. 4. 미세구조의 변화, 정세포 체적의 감소, 정세포 및 정자 핵에 표지되는 금 입자의 증가와 이들 현상이 나타나는 동시성으로 볼 때 정세포 핵의 형태변화의 내용은 응축이고 이는 F-actin의 탈중합 반응에 의한 G-액틴의 생성이 원인일 것으로 사료된다.

• Nuclear Engineering and Technology
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• 제46권3호
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• pp.313-342
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• 2014

A Nuclear Energy Agency (NEA), Organization for Economic Co-operation and Development (OECD) benchmark for Uncertainty Analysis in Modeling (UAM) is defined in order to facilitate the development and validation of available uncertainty analysis and sensitivity analysis methods for best-estimate Light water Reactor (LWR) design and safety calculations. The benchmark has been named the OECD/NEA UAM-LWR benchmark, and has been divided into three phases each of which focuses on a different portion of the uncertainty propagation in LWR multi-physics and multi-scale analysis. Several different reactor cases are modeled at various phases of a reactor calculation. This paper discusses Phase I, known as the "Neutronics Phase", which is devoted mostly to the propagation of nuclear data (cross-section) uncertainty throughout steady-state stand-alone neutronics core calculations. Three reactor systems (for which design, operation and measured data are available) are rigorously studied in this benchmark: Peach Bottom Unit 2 BWR, Three Mile Island Unit 1 PWR, and VVER-1000 Kozloduy-6/Kalinin-3. Additional measured data is analyzed such as the KRITZ LEU criticality experiments and the SNEAK-7A and 7B experiments of the Karlsruhe Fast Critical Facility. Analyzed results include the top five neutron-nuclide reactions, which contribute the most to the prediction uncertainty in keff, as well as the uncertainty in key parameters of neutronics analysis such as microscopic and macroscopic cross-sections, six-group decay constants, assembly discontinuity factors, and axial and radial core power distributions. Conclusions are drawn regarding where further studies should be done to reduce uncertainties in key nuclide reaction uncertainties (i.e.: $^{238}U$ radiative capture and inelastic scattering (n, n') as well as the average number of neutrons released per fission event of $^{239}Pu$).

• Nuclear Engineering and Technology
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• 제31권6호
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• pp.595-607
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• 1999

The reaction cross-sections of $^{nat}$Ti(p,X)$^{48}$ V, $^{nat}$Fe(p,X)$^{56}$ Co, $^{nat}$Cu(p,X)$^{65}$ Zn and $^{nat}$Mo(p,X)$^{96}$ Tc for TLA application are calculated in the frame of the ECIS-GNASH code system up to 60 MeV. The calculated results are compared with the experimental data taken from the EXFOR at the NEA Data Bank. A preliminary calculation with the global optical parameters of Varner et al. shows considerable differences from the experimental data at low energy range. The global optical parameters for the imaginary volume potential and the diffuseness of the imaginary potential are adjusted to achieve a better description of the experimental data in the vicinities of peak position below 16 MeV. 16 MeV.

• 천문학회보
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• 제42권2호
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• pp.65.5-66
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• 2017

In the history of astronomy, observed data were interpreted very frequently based upon data measured at laboratories. For example, all the spectroscopic observations were understood via spectroscopic measurements on nuclei, atoms, and molecules. Recently, computational astrophysics plays a role of bridging experimental data to observations, in particular via numerical modeling of complex astronomical phenomena. This presentation focuses on computational nuclear astrophysics that connects experimental data on nuclei to high-energy observation data obtained by X-ray and gamma-ray telescopes. As an example case, X-ray burst will be discussed. In this phenomenon, observed X-ray light curves and spectra can be modeled by stellar evolution calculations that take nuclear reactions of rare isotopes as input information. This presentation also works as an introduction to the following presentation that will provide more detailed discussion on the experimental aspect of X-ray burst.

• 한국의학물리학회:학술대회논문집
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• 한국의학물리학회 2002년도 Proceedings
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• pp.186-188
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• 2002

An improved analytical model has been developed to calculate an accurate Bragg curve of proton beam with an arbitrary energy. The model takes the transport of the secondary protons produced by the nuclear inelastic reactions into account. By the model, measured Bragg curves of proton beams with ten energies between 250 and 70 MeV are reproduced well. It will serve to obtain fundamental data for treatment planning and for energy scanning.

• 한국진공학회지
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• 제1권1호
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• pp.96-99
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• 1992

텅스텐 표면의 (110)면에 흡착된 산소량을 18O(P,$\alpha$)15N 핵반응으로 직접 측정하여 미세분석 하였다. Van de Graaff 가속기로 양성자를 가속시켜 시료 표면 가까이에 있는 원 자와 충돌시켜 생성되는 $\alpha$ 입자를 측정함으로써 표면에 있는 미소량의 원소도 측정이 가능 했다. $\alpha$ 입자의 수율은 oxygen exposure에 비례하였는데 coverage ($ heta$)는 5 Langmuir에서 0.5가 되었고, 15 Langmuir에서 포화되었다.

• 대한화학회지
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• 제24권3호
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• pp.245-249
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• 1980

도데칸에 녹인 아세틸아세톤과 트리부틸인산으로 묽은 질산우라닐수용액에서 우라늄(Ⅵ)을 추출했다. pH 1 이상에서 이 혼합추출제의 상승적 효과가 관측되었다. 추출되는 화학종은 1:2:1 및 1:2:2 우라닐-아세틸 아세톤-트리부틸 인산착물이다. 이들 반응의 추출정수들을 측정하였다.

• Nuclear Engineering and Technology
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• 제6권1호
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• pp.23-26
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• 1974

염화 메탄 슬포닐의 할로겐 교환반응을 무수아세톤, 아세토니트릴, 메타놀 용매중에서 행하여 반응속도상수와 활성화파라메터를 구하였다. 친핵성도는 Cl->Br>I- 순서로 감소하였으며, 용매변화에 따른 염소이온과의 반응 속도는 ($CH_3$)$_2$CO>$CH_3$CN》$CH_3$OH의 순서로 감소하였다. 실험결과를 초기상태 탈용매화의 용이함과 천이상태 용매화의 안정성으로 설명하였다.

• Nuclear Engineering and Technology
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• 제38권8호
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• pp.733-752
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• 2006

Severe accidents in PWRs are characterized by a continuously changing geometry of the core due to chemical reactions, melting and mechanical failure of the rods and other structures. These local variations of the porosity and other parameters lead to multi-dimensionnal flows and heat transfers. In this paper, a comprehensive set of multi-dimensionnal models describing heat transfers, thermal-hydraulics and melt relocation in a reactor vessel is presented. Those models are suitable for the core description during a severe accident transient. A series of applications at the reactor scale shows the benefits of using such models.