• Title/Summary/Keyword: 원자분포

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Thermal Transient Response of a PWR Pressurizer Vessel Wall for the Inadvertent Auxiliary Spray Transient (PWR 가압기에서 오동작 보조살수 과도시 용기벽의 열적 과도응답)

  • Jo, Jong-Chull;Lee, Sang-Kyoon;Shin, Won-Ky;Cho, Jin-Ho
    • Nuclear Engineering and Technology
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    • v.23 no.2
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    • pp.183-199
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    • 1991
  • Transient response of temperature distributions in a Pressurized Water Reactor (PWR) pressurizer vessel wall for the Inadvertent Auxiliary Spray transient has been analyzed with conservatism accounted for the resulting thermal stresses in the regions of the vessel wall which are wetted by the spray water droplets. In order to determine the forced convective heat transfer coefficient at the inner boundary surface of vessel wall where the droplets impinge on and flow down, the transient temperatures of spray droplets when they reach the inner surface of the vessel wall after travelling from the spray nozzle through the pressurizer interior space occupied with the saturated steam-noncondensable hydrogen gas mixture have been predicted. The transient temperature distributions in the vessel wall have been obtained by using the finite element method, and the typical results have been provided. It has been shown that the results of thermal analysis are consistent with representation of the input transient and have plausible physical meaning.

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Surface Properties of Glutathione Layer Formed on Gold Surfaces (금 표면 위에 형성된 글루타싸이온 층의 표면 물성)

  • Park, Jin-Won
    • Korean Chemical Engineering Research
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    • v.50 no.2
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    • pp.379-384
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    • 2012
  • It is investigated that that the physical properties of Glutathione layer formed on gold surfaces may make an effect on the distribution of either gold particle adsorbed to the $TiO_2$ surface or vice versa with the adjustment of the electrostatic interactions. For the investigation, the atomic force microscope (AFM) was used to measure the surface forces between the surfaces as a function of the salt concentration and pH value. With the Derjaguin-Landau-Verwey-Overbeek (DLVO) theory, the forces were quantitatively analyzed to acquire the surface potential and charge density of the surfaces for each salt concentration and each pH value. The surface potential and charge density dependence on the salt concentration was described with the law of mass action, and the pH dependence was explained with the ionizable groups on the surface. The salt concentration dependence of the surface properties, found from the measurement at pH 8 and 11, was consistent with the prediction from the law. It was found that the Glutathione layer had higher values for the surface charge densities and potentials than the titanium dioxide surfaces at pH 8 and 11, which may be attributed to the ionized-functional-groups of the Glutathione layer.

DNBR Sensitivities to Variations in PWR Operating Parameters (가압경수로의 운전변수 변화에 대한 DNBR의 민감도)

  • Hyun Koon Kim;Ki In Han
    • Nuclear Engineering and Technology
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    • v.15 no.4
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    • pp.236-247
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    • 1983
  • Analyzed are the the DNBR(Departure from Nucleate Boiling Ratio) sensitivities to variations in various PWR operating parameters utilizing the Korea Nuclear Unit 1(KNU-1) design and operating data. Studied parameters in the analysis are core power level, system pressure, core inlet flow rate, core inlet temperature, enthalpy rise hot channel factor, and axial power peaking factor and axial offset. The calculations are performed using the steady state and transient thermal-hydraulics computer program, COBRA-IV-K, which is the revised version of COBRA-IV-i that has been adapted, partially modified and verified at KAERI. A reference case is established based on the design and operating condition of the KNU-1 reactor core, and this provides a basis for the subsequent sensitivity analysis. From the calculation results it is concluded that the most sensitive parameter in the DNBR thermal design is the coolant core inlet temperature while the axial power peaking factor is the least sensitive.

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A Molecular Dynamics Study on the Liquid-Glass-Crystalline Transition of Lennard-Jones System (한 Lennard-jones 시스템의 액체-유리-결정 전이에 관한 분자동역학 연구)

  • Chang, Hyeon-Gu;Lee, Jong-Gil;Kim, Sun-Gwang
    • Korean Journal of Materials Research
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    • v.8 no.8
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    • pp.678-684
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    • 1998
  • By means of constant- pressure molecular dynamics simulations, we studied the liquid- glass- crystalline transition of a system composed of Lennard- Jones particles with periodic boundary conditions. Atomic volume and enthalpy were calculated as functions of temperature during heating and cooling processes. The Wendt- Abraham ratio derived from radial distribution function and the angular distribution function characterizing short range order were analyzed to distinguish between liquid, glass and crystalline states. A liquid phase resulting from a slow heating of an initial fee crystal amorphized on fast quench, but it crystallized on slow quench. When slowly heated, the amorphous phase from fast quench crystallized into an fee structure. A system with free surface was shown to melt from the surface inward at a lower temperature than bulk system and to have a strong tendency for crystallization even during a fast quench from a liquid state.

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Study on Distribution of Elemental Concentration with a Different Depth of River Sediment using Neutron Activation Analysis (중성자 방사화 분석을 이용한 하천 침전물의 깊이에 따른 원소의 함량분포 연구)

  • Kim, Hyeon-Soo;Im, Hye-Ran;Kim, Yong-Uhn;Moon, Jong-Hwa
    • Analytical Science and Technology
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    • v.16 no.3
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    • pp.232-239
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    • 2003
  • The river sediments were collected from 4 points of Seoknam river, one point of Miho river and one point of the joining area of two rivers. For preparation of sample, three sediment samples were collected for the surface, middle and lower part of the sediment at each sampling point. The elemental concentrations were analyzed by neutron activation analysis using HANARO research reactor at Korea Atomic Energy Research Institute, and the concentrations of 30 elements were determined by the relative method using standard reference material of NIST. As a result of analysis, it was found that when the examination and prediction of contamination distribution about the site where the contamination site of river is connected to the lower river is done, the specific gravity of elements which is contained in the sediment and the speed of a current of river should be considered and also found that when the samples for concentration analysis in the river sediments are collected, for the establishment of regional representatives in samples, the range of sampling depth should be determined considering the specific gravity of elements and the speed of a current.

Numerical Analysis of Flow Distribution in the Scaled-down APR+ Using Two-Equation Turbulence Models (2방정식 난류모델을 이용한 축소 APR+ 내부 유동분포 수치해석)

  • Lee, Gong Hee;Bang, Young Seok;Cheong, Ae Ju
    • Korean Journal of Air-Conditioning and Refrigeration Engineering
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    • v.27 no.4
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    • pp.220-227
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    • 2015
  • Complex thermal hydraulic characteristics exist inside the reactor because the reactor internals consist of fuel assembly, internal structures and so on. In this study, to examine the effect of Reynolds-Averaged Navier-Stokes (RANS)-based two-equation turbulence models in the analysis of flow distribution inside a 1/5 scaled-down APR+, simulation was performed using the commercial computational fluid dynamics software, ANSYS CFX R.13 and the predicted results were compared with the measured data. It was concluded that reactor internal flow pattern was locally different depending on the turbulence models. In addition, the prediction accuracy of k-${\varepsilon}$ model was superior to that of other two-equation turbulence models and this model predicted the relatively uniform distribution of core inlet flow rate.

The Effect of Analysis Variables on the Failure Probability of the Reactor Pressure Vessel by Pressurized Thermal Shock (가압열충격에 의한 원자로 압력용기의 파손확률에 미치는 해석변수의 영향)

  • Jang, Chang-Heui;Jhung, Myung-Jo;Kang, Suk-Chull;Choi, Young-Hwan
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.28 no.6
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    • pp.693-700
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    • 2004
  • The probabilistic fracture mechanics(PFM) is a useful analytical tool to assess the integrity of reactor pressure vessel(RPV) at the event of pressurized thermal shock(PTS). In PFM, the probabilities of flaw initiation and propagation are estimated by comparing the applied stress intensity factor with the fracture toughness calculated by the simulation of various stochastic variables. It is known that the results of PFM analyses are dependent on the choice of the stochastic parameters and assumptions. Of the various variables and assumptions, we investigated the effects of the RT$_{NDT}$ shift equations, fracture toughness curves, and flaw distributions on the PFM results for the three PTS transients. The results showed that the combined effects of the RT$_{NDT}$ shift equations and fracture toughness curves are complicated and dependent on the characteristics of the transients, the chemistry of the materials, the fast neutron fluence, and so on.

An Investigation of Debris Configuration and Melt-Water Interaction in Steam Explosion Experiments using $ZrO_2$ (원자로 물질의 $ZrO_2$를 이용한 증기폭발 실험에서 용융물 거동 및 데브리의 분포)

  • Song, J.H.;Kim, H.D.;Hong, S.W.;Park, I.K.;Shin, Y.S.;Min, B.T.;Chang, Y.J.
    • Proceedings of the KSME Conference
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    • 2001.06e
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    • pp.57-62
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    • 2001
  • Korea Atomic Energy Research Institute (KAERI) launched an intermediate scale steam explosion experiment named Test for Real cOrium Interaction with water (TROI) using reactor material to investigate whether the corium would lead to energetic steam explosion when interacted with cold water at low pressure. The melt-water interaction is confined in a pressure vessel with the multi-dimensional fuel and water pool geometry. The cold crucible technology, where the mixture of powder in a water-cooled cage is heated by high frequency induction, is employed. In this paper, results of the first series of tests ($TROI-1{\sim}5$) were discussed. The ZrO2 jets with 5kg mass and 5cm diameter were poured into the 67cm deep water pool at $30{\sim}95^{\circ}C$. Either spontaneous steam explosions or quenching was observed. The morphology of debris and pressure wave profiles clearly indicates the each case.

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Application of computer graphics for a preliminary evaluation of dismantling scenario (컴퓨터 그래픽스를 이용한 해체 공정 시나리오 예비 평가)

  • Park Hee-Seong;Kim Sung-Kyun;Lee Kyne-Woo;Jung Chong-Hun;Park Jin-Ho;Jin Seong-Il
    • Proceedings of the Korea Information Processing Society Conference
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    • 2006.05a
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    • pp.1311-1314
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    • 2006
  • 원자력 시설 및 연구용 원자로 해체 시 해체 공정의 효율성을 증진시키기 위해 컴퓨터 그래픽스를 이용한 해체 공정의 최적화 연구가 수행되었다. 애니메이션 설계를 위해 해체 시설 및 구조물과 해체 장비의 모델링이 완료되었으며, 방사능에 오염된 대상물의 방사능 분포도를 위치별, 준위별로 확인할 수 있도록 3 차원으로 나타내었다. 해체 일정과 해체 폐기물량 그리고 해체 비용을 모사하기 위해 각 정보들에 대한 평가식과 가중치 값을 도출하였다. 연구로 1 호기 Thermal column 을 대상으로 애니메이션을 통한 해체 공정절차 시각화와 단위 해체 공정 시나리오를 수행한 결과 애니메이션의 경우 해체 현장과 동일하게 모델링 되어 현장 작업자들이 해체 공정 절차를 쉽게 이해할 수 있다는 것을 확인하였으며, 시나리오 별 해체 소요시간과 폐기물량 그리고 해체 비용의 경우 정상적으로 모사가 수행됨으로써 단위 해체 공정에 대한 최적의 시나리오를 평가 할 수 있는 기초 연구의 틀을 마련하였다. 본 시스템은 해체 관리자, 해체 시스템 분석가, 해체 현장 감독과 해체 작업자들의 중요한 협업도구로 활용될 것으로 사료된다.

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Dose Distribution for Eye Shielding Block In 6 MV Photon Beam Therapy (6 MV 광자선치료에서 안구차폐기구의 제작과 선량분포 측정)

  • Lee, Kyung-Ja
    • Radiation Oncology Journal
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    • v.10 no.2
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    • pp.155-161
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    • 1992
  • The eye lens is known to be radiosensitive organ and catarat can be induced by relatively low dose of radiation. In the treatment of head and neck tumors, shielding blocks are frequently used to minimize dose on sensitive organs. The shielding block, which is made of high atomic number materials (cerrobend), produce significant dose perturbations in megavoltage photon beams. The effects of these perturbations of eye shielding blocks are measured with film and ion chambers for the treatment of head and neck malignancies. Optimum parameters for the treatment are suggested.

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