• Title/Summary/Keyword: atomic distribution

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원자짝 분포 함수를 이용한 칼슘 실리케이트 경화체의 나노 구조 변형 거동 해석 (Nanostructural Deformation Analysis of Tricalcium Silicate Paste by Atomic Pair Distribution Function)

  • 배성철;장유현;지현석
    • 한국건축시공학회:학술대회논문집
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    • 한국건축시공학회 2016년도 추계 학술논문 발표대회
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    • pp.94-95
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    • 2016
  • Calcium Silicate Hydrate (C-S-H), which takes up most of the hydration products of Portland Cement (PC), has the greatest impact on the mechanical behavior and strength development of concrete. The exact mechanism of its deformation, however, has not yet been elucidated. The present study aims to demonstrate the mechanism of nano-deformation behavior of C-S-H in tricalcium silicate paste under compressive loading, unloading and reloading by interpreting atomic pair distribution function (PDF) based on synchrotron X-ray scattering. The strain of the tricalcium silicate paste for a short-range of 0 ~ 20 Å under compressive load exhibited two stages, I) nano-packing of interlayer of C-S-H and II) micro-packing of C-S-H globules, whereas the deformation for a long-range order of 20 ~ 40 Å was similar to that of a calcium hydroxide phase measured by Bragg peak shift. Moreover, the residual strains due to the plastic deformation of C-S-H was clearly observed.

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Determination of Gamma-Ray Depth-Dose Distribution in a Polyethylene Sphere Phantom

  • Ha, Chung-Woo;Jun, Jae-Shik;Park, Chae-Shik
    • Nuclear Engineering and Technology
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    • 제7권4호
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    • pp.285-293
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    • 1975
  • 30cm 직경 포리에티렌 구체내의 길이에 따른 선량분포중 최대흡수선량인 흡수선량지수를 주어진 감마방사선장내에서 열형광선량계를 이용하여 결정하였다. 열형광선량계내의 흡수선량과 주위 눈질내의 흡수선량간의 환산은 Burlin의 general cavity theory에 의거하였다. $^{60}$Co과 $^{137}$Cs에 의한 방사선장에서 구체내 최대흡수선량은 구체표면으로 부터 각각 0.5cm 및 0.3cm에 나타났으며 이 결과는 이론적으로 예상한 분포특성과 아주 근사하였다.

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Cs-137 distribution around Kori Nuclear Power Plant

  • Lee, H.;Kang, H.S.;Choi, H.J.;Yu, D.H.;Lim, K.M.;Choi, Y.H.
    • Journal of Radiation Protection and Research
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    • 제28권4호
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    • pp.349-351
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    • 2003
  • To ensure the safety of the currently operating nuclear power plant, the Periodic Safety Review program has been conducted. In PSR program, the cumulative behavior of the radionuclide that might be released from the power plant is addressed. The Cs-137 in soil around Kori nuclear power plant was investigated. The soil sample was analyzed and compared with the reference area. The model calculation explained the depth profile of Cs-137.

Preparation and Characterization of Stable Dispersions of Ni Nanoparticles

  • Lee, Eun-Hee;Lee, Min-Ku;Rhee, Chang-Kyu
    • 한국분말야금학회:학술대회논문집
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    • 한국분말야금학회 2006년도 Extended Abstracts of 2006 POWDER METALLURGY World Congress Part 1
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    • pp.413-414
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    • 2006
  • The effects of several experimental parameters on the formation of stable Ni nanoparticles dispersion were investigated. The suspensions of Ni nanoparticles were produced in organic solvents using Hypermer KD-2 as a dispersant. The transmission profiles, particle size distribution, zeta potential, and visual inspection results were used to discuss the stability of the dispersion. The optimal conditions for the formation of stable dispersion are evaluated.

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The RTD Measurement on a Submerged Bio-Reactor using a Radioisotope Tracer and the RTD Analysis

  • Seungkwon Shin;Kim, Jongbum;Sunghee Jung;Joonha Jin
    • International Journal of Control, Automation, and Systems
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    • 제1권2호
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    • pp.210-214
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    • 2003
  • This paper presents a residence time distribution (RTD) measurement method using a radioisotope tracer and the estimation method of RTD model parameters to analyze a submerged bio-reactor. The mathematical RTD models have been investigated to represent the flow behavior and the existence of stagnant regions in the reactor. Knowing the parameters of the RTD model is important for understanding the mixing characteristics of a reactor The radioisotope tracer experiment was carried out by injecting a radioisotope tracer as a pulse into the inlet of the reactor and recording the change of its concentration at the outlet of the reactor to obtain the experimental RTD response. The parameter estimation was performed by the Levenberg-Marquardt optimization algorithm. The proposed scheme allowed the parameter estimation of RTD model suggested by Adler-Hovorka with very low deviations. The estimation procedure is shown to lead to accurate estimation of the RTD parameters and to a good agreement between experimental and simulated response.

INFLUENCE OF MECHANICAL ALLOYING ATMOSPHERES ON THE MICROSTRUCTURES AND MECHANICAL PROPERTIES OF 15Cr ODS STEELS

  • Noh, Sanghoon;Choi, Byoung-Kwon;Kang, Suk Hoon;Kim, Tae Kyu
    • Nuclear Engineering and Technology
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    • 제46권6호
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    • pp.857-862
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    • 2014
  • Mechanical alloying under various gas atmospheres such as Ar, an Ar-$H_2$ mixture, and He gases were carried out, and its effects on the powder properties, microstructure and mechanical properties of ODS ferritic steels were investigated. Hot isostatic pressing and hot rolling processes were employed to consolidate the ODS steel plates. While the mechanical alloyed powder in He had a high oxygen concentration, a milling in Ar showed fine particle diameters with comparably low oxygen concentration. The microstructural observation revealed that low oxygen concentration contributed to the formation of fine grains and homogeneous oxide particle distribution by the Y-Ti-O complex oxides. A milling in Ar was sufficient to lower the oxygen concentration, and this led a high tensile strength and fracture elongation at a high temperature. It is concluded that the mechanical alloying atmosphere affects oxygen concentration as well as powder particle properties. This leads to a homogeneous grain and oxide particle distribution with excellent creep strength at high temperature.

Tissue distribution, excretion and effects on genotoxicity of tritium following oral administration to rats

  • Lee, Jei Ha;Kim, Cha Soon;Choi, Soo Im;Kim, Rae-Kwon;Kim, Ji Young;Nam, Seon Young;Jin, Young Woo;Kim, In Gyu
    • Nuclear Engineering and Technology
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    • 제51권1호
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    • pp.303-309
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    • 2019
  • Tritium is an important nuclide that must be monitored for radiation safety management. In this study, HTO was orally administered to rats at the level of 37 kBq ($1{\mu}Ci$) or 370 kBq ($10{\mu}Ci$) to examine tissue distribution and excretion levels. After sacrifice, wet and dry tissue samples were weighed and analyzed for tissue free-water tritium (TFWT) and organically bound tritium (OBT). The mean tissue concentrations of TFWT (OBT) were 30.9 (17.8) and 4.4 (8.1) Bq/g on days 7 and 13 at the 37 kBq level and 30.8 (64.6) Bq/g on day 17 at the 370 kBq level. To assess the cytogenetic damage due to tritium exposure, a cytokinesis-blocked micronucleus (MN) assay was performed in blood samples from rats exposed to HTO for 14 and 21 days after oral administration. There was no significant difference in the MN frequencies between the control and exposed rats.

Development of advanced rigorous two-step code system for evaluation of radioactive waste with high-resolution activation calculation

  • Kim, Do Hyun;Kim, Jiseok;Lee, Han Rim;Sun, Gwang Min;Shin, Chang Ho;Kim, Jong Kyung
    • Nuclear Engineering and Technology
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    • 제53권6호
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    • pp.2011-2018
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    • 2021
  • Nowadays, evaluation of amounts and distributions of radioactive waste is an important preparatory step in the process of nuclear reactor decommissioning. For tentative estimation of radioactive waste, a cell-based rigorous 2 step (R2S) method usually is used; however, a poor resolution caused by the averaged flux and spectrum in a cell is still a great challenge because of leading to underestimated or overestimated results. To overcome the poor resolution, several systems were introduced. Neither system, however, provides any function for evaluation of radioactive waste amount and distribution. Thus, it is additionally required to classify radioactive waste based on the results of activation calculation. In this study, the advanced R2S (AR2S) system was developed. To verify the performance of the system, its results for a verification problem were compared with those of the cell-based R2S method. The results showed good agreement, which is to say, within 2.0% relative error. Also, several characteristics of fine/coarse mesh were analyzed. To demonstrate the performance of the AR2S system, the radioactive waste from the Japan Power Demonstration Reactor (JPDR) was estimated, and the result indicated a high-resolution distribution. Therefore, it is expected that the AR2S system will prove useful for precise evaluation of radioactive waste.

Determination of dosimetric dependence for effective atomic number of LDR brachytherapy seed capsule by Monte Carlo simulation

  • Berkay Camgoz;Dilara Tarim
    • Nuclear Engineering and Technology
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    • 제55권8호
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    • pp.2734-2741
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    • 2023
  • Brachytherapy is a special case of radiotherapy. It should be arranged according to some principles in medical radiation applications and radiation physics. The primary principle is to use as low as reasonably achievable dose in all ionizing radiation applications for diagnostic and therapeutic treatments. Dosimetric distributions are dependent on radioactive source properties and radiation-matter interactions in an absorber medium such as phantom or tissue. In this consideration, the geometrical structure and material of the seed capsule, which surrounds a radioactive material, are directly responsible for isodose profiles and dosimetric functions. In this study, the radiometric properties of capsule material were investigated on dose distribution in a water phantom by changing its nuclear properties using the EGSnrc Monte Carlo (MC) simulation code. Effective atomic numbers of hypothetic mixtures were calculated by using different elements with several fractions for capsule material. Model 6711 brachytherapy seed was modeled by EGSnrc/Dosrcnrc Code and dosimetric functions were calculated. As a result, dosimetric parameters of hypothetic sources have been acquired in large-scale atomic number. Dosimetric deviations between the data of hypothetic seeds and the original one were analyzed. Unit dose (Gy/Particle) distributions belonging to different types of material in seed capsule have remarkably differed from the original capsule's data. Capsule type is major variable to manage the expected dose profile and isodose distribution around a seed. This study shows us systematically varied scale of material type (cross section or effective atomic number dependent) offers selective material usage in production of seed capsules for the expected isodose profile of a specific source.

Effects of Aperture Densitv Distribution on the Flow Through a Rock Fracture with Line-Source and Line-Collection

  • Park, Chung-Kyun;Hahn, Pil-So
    • Nuclear Engineering and Technology
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    • 제30권6호
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    • pp.485-495
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    • 1998
  • Migration characteristics of tracers in a rock fracture in a case of line-source and line-collection was studied. The fracture plane was discretized into a square mesh to which variable apertures were assigned. The spatially varying apertures of a fracture were generated using a geostatistical method, based on a given aperture probability density distribution and a specified spatial correlation length. The flow potential and pressure at each node were computed. Calculations showed that fluid flow occurs predominantly through a few preferred paths. Hence, the large range of apertures in the fracture gives rise to flow channeling. The solute transport was calculated using a particle tracking method. The migration plumes of tracer between injection line and withdrawal line are displayed in contour plots. The elution curves are shown to be controlled by the aperture density distribution and to be insensitive to statistical realization and spatial correlation length.

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