• 제목/요약/키워드: atomic ratio

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국내탄의 석탄암석학적 특성 (Coal Petrological Characteristics of Korean Coal)

  • 박홍수;박석환
    • 자원환경지질
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    • 제22권2호
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    • pp.141-150
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    • 1989
  • In order to make economic and geological evaluation of coal in Korea, proximate and ultimate analyses were carried out as well as coal petrological studies such as maceral analyses, vitrinite reflectance and sporinite fluorescence measurement. The coeffcient of correlation between each factor of both conventional utilization and coal petrological parameters were studied as in Table 5 and 6. Their conclusions were as follow: (1) for anthracite, the good parameters of coal rank are mean vitrinite reflectance, carbon content, hydrogen content and H/C atomic ratio: (2) for brown coal and sub-bituminous coal, the good parameters of coal rank are carbon content, calorific value, moisture content, hydrogen content, oxygen content and O/C atomic ratio as well as vitrinite reflectance and sporinite fluorescence. An attempt is made to infer the coalforming environment by utilization of coal petrological analyses and to make comparison of coal analyses with proximate and ultimate analyses throughout the island arc region including Japan, Philippine and Indonesia and continental region including USA, Canada and Australia. As a result, meceral composition of Paleozoic and Mesozoic anthracite are similar to that of the Paleozoic continental coals, which were formed under dry conditions or low water table, but the coalification degree suddenly increased during Daebo orogeny (middle Jurassic to lower Cretaceous). The Tertiary coal resembles those of Tertiary island arc region coal characterized by higher calorific value, volatile matter content and H/C atomic ratio and by the formation of coal under wet conditions or higher water table.

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화학증착법에 의하여 제조된 탄화지르코늄 코팅층의 물성 (Properties of Chemical Vapor Deposited ZrC coating layer for TRISO Coated Fuel Particle)

  • 김준규;금이슬;최두진;이영우;박지연
    • 한국세라믹학회지
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    • 제44권10호
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    • pp.580-584
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    • 2007
  • The ZrC layer instead of SiC layer is a critical and essential layer in TRISO coated fuel particles since it is a protective layer against diffusion of fission products and provides mechanical strength for the fuel particle. In this study, we carried out computational simulation before actual experiment. With these simulation results, Zirconium carbide (ZrC) films were chemically vapor deposited on $ZrO_2$ substrate using zirconium tetrachloride $(ZrCl_4),\;CH_4$ as a source and $H_2$ dilution gas, respectively. The change of input gas ratio was correlated with growth rate and morphology of deposited ZrC films. The growth rate of ZrC films increased as the input gas ratio decreased. The microstructure of ZrC films was changed with input gas ratio; small granular type grain structure was exhibited at the low input gas ratio. Angular type structure of increased grain size was observed at the high input gas ratio.

Recent Developments in Nuclear Forensic and Nuclear Safeguards Analysis Using Mass Spectrometry

  • Song, Kyuseok;Park, Jong-Ho;Lee, Chi-Gyu;Han, Sun-Ho
    • Mass Spectrometry Letters
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    • 제7권2호
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    • pp.31-40
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    • 2016
  • The analysis of nuclear materials and environmental samples is an important issue in nuclear safeguards and nuclear forensics. An analysis technique for safeguard samples has been developed for the detection of undeclared nuclear activities and verification of declared nuclear activities, while nuclear forensics has been developed to trace the origins and intended use of illicitly trafficked nuclear or radioactive materials. In these two analytical techniques, mass spectrometry has played an important role in determining the isotope ratio of various nuclides, contents of trace elements, and production dates. These two techniques typically use similar analytical instruments, but the analytical procedure and the interpretation of analytical results differ depending on the analytical purpose. The isotopic ratio of the samples is considered the most important result in an environmental sample analysis, while age dating and impurity analysis may also be important for nuclear forensics. In this review, important aspects of these techniques are compared and the role of mass spectrometry, along with recent progress in related technologies, are discussed.

Investigating Dynamic Parameters in HWZPR Based on the Experimental and Calculated Results

  • Nasrazadani, Zahra;Behfarnia, Manochehr;Khorsandi, Jamshid;Mirvakili, Mohammad
    • Nuclear Engineering and Technology
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    • 제48권5호
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    • pp.1120-1125
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    • 2016
  • The neutron decay constant, ${\alpha}$, and effective delayed neutron fraction, ${\beta}_{eff}$, are important parameters for the control of the dynamic behavior of nuclear reactors. For the heavy water zero power reactor (HWZPR), this document describes the measurements of the neutron decay constant by noise analysis methods, including variance to mean (VTM) ratio and endogenous pulse source (EPS) methods. The measured ${\alpha}$ is successively used to determine the experimental value of the effective delayed neutron fraction as well. According to the experimental results, ${\beta}_{eff}$ of the HWZPR reactor under study is equal to 7.84e-3. This value is finally used to validate the calculation of the effective delayed neutron fraction by the Monte Carlo methods that are discussed in the document. Using the Monte Carlo N-Particle (MCNP)-4C code, a ${\beta}_{eff}$ value of 7.58e-3 was obtained for the reactor under study. Thus, the relative difference between the ${\beta}_{eff}$ values determined experimentally and by Monte Carlo methods was estimated to be < 4%.

Probabilistic Estimation of LMR Fuel Cladding Performance Under Transient Conditions

  • Kwon, Hyoung-Mun;Lee, Dong-Uk;Lee, Byung-Oon;Kim, Young ll;Kim, Yong-Soo
    • Nuclear Engineering and Technology
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    • 제35권2호
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    • pp.144-153
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    • 2003
  • The object of this paper is the probabilistic failure analysis on the cladding performance of WPF(Whole Pin Furnace) test fuel pins under transient conditions, and analysis of the KALIMER fuel pin using the preceding analysis. The cumulative damage estimation and Weibull probability estimation of WPF test are performed. The probabilistic method was adapted for these analyses to determine the effective thickness thinning due to eutectic penetration depth. In the results, it is difficult to assume that a brittle layer depth made by eutectic reaction is all of the thickness reduction due to cladding thinning. About 93% cladding thinning of the eutectic penetration depth is favorable as an effective thickness of cladding. And the unreliability of the KALIMER driver fuel pin under the same WPF test condition is lower than that of the WPF pin because of the higher plenum-fuel volume ratio and lower cladding inner radius vs. thickness ratio. KALIMER fuel pin developed from conceptual design has a more stable transient performance for a failure mechanism due to fission gas buildup than the WPF pin.

Recycling of Li2ZrO3 as LiCl and ZrO2 via a Chlorination Technique

  • Jeon, Min Ku;Kim, Sung-Wook;Lee, Keun-Young;Choi, Eun-Young
    • 방사성폐기물학회지
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    • 제19권2호
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    • pp.271-278
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    • 2021
  • In this study, a chlorination technique for recycling Li2ZrO3, a reaction product of ZrO2-assisted rinsing process, was investigated to minimize the generation of secondary radioactive pyroprocessing waste. It was found that the reaction temperature was a key parameter that determined the reaction rate and maximum conversion ratio. In the temperature range of 400-600℃, an increase in the reaction temperature resulted in a profound increase in the reaction rate. Hence, according to the experimental results, a reaction temperature of at least 450℃ was proposed to ensure a Li2ZrO3 conversion ratio that exceeded 80% within 8 h of the reaction time. The activation energy was found to be 102 ± 2 kJ·mol-1·K-1 between 450 and 500℃. The formation of LiCl and ZrO2 as reaction products was confirmed by X-ray diffraction analysis. The experimental results obtained at various total flow rates revealed that the overall reaction rate depends on the Cl2 mass transfer rate in the experimental condition. The results of this study prove that the chlorination technique provides a solution to minimize the amount of radioactive waste generated during the ZrO2-assisted rinsing process.

Predicting Damage in a Concrete Structure Using Acoustic Emission and Electrical Resistivity for a Low and Intermediate Level Nuclear Waste Repository

  • Hong, Chang-Ho;Kim, Jin-Seop;Lee, Hang-Lo;Cho, Dong-Keun
    • 방사성폐기물학회지
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    • 제19권2호
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    • pp.197-204
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    • 2021
  • In this study, the well-known non-destructive acoustic emission (AE) and electrical resistivity methods were employed to predict quantitative damage in the silo structure of the Wolsong Low and Intermediate Level Radioactive Waste Disposal Center (WLDC), Gyeongju, South Korea. Brazilian tensile test was conducted with a fully saturated specimen with a composition identical to that of the WLDC silo concrete. Bi-axial strain gauges, AE sensors, and electrodes were attached to the surface of the specimen to monitor changes. Both the AE hit and electrical resistance values helped in the anticipation of imminent specimen failure, which was further confirmed using a strain gauge. The quantitative damage (or damage variable) was defined according to the AE hits and electrical resistance and analyzed with stress ratio variations. Approximately 75% of the damage occurred when the stress ratio exceeded 0.5. Quantitative damage from AE hits and electrical resistance showed a good correlation (R = 0.988, RMSE = 0.044). This implies that AE and electrical resistivity can be complementarily used for damage assessment of the structure. In future, damage to dry and heated specimens will be examined using AE hits and electrical resistance, and the results will be compared with those from this study.

Experimental investigation of jet pump performance used for high flow amplification in nuclear applications

  • Vimal Kotak;Anil Pathrose;Samiran Sengupta;Sugilal Gopalkrishnan;Sujay Bhattacharya
    • Nuclear Engineering and Technology
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    • 제55권10호
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    • pp.3549-3558
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    • 2023
  • The jet pump can be used in a test device of a nuclear reactor for high flow amplification as it reduces inlet flow requirement and thereby size of the process components. In the present work, a miniature jet pump was designed to meet high flow amplification greater than 3. Subsequently, experiments were carried out using a test setup for design validation and performance evaluation of the jet pump for different parameters. It was observed that a minimum pressure of 0.6 bar (g) was required for the secondary fluid inside the jet pump to ensure cavitation free performance at high amplification. Spacing between the nozzle tip and the mixing chamber entry point had significant effect on the performance of the jet pump. Variation in primary flow, temperature and area ratio also affected the performance. It was observed that at high flow amplification, the analytical solution differed significantly from experimental results due to very large velocities encountered in the miniature size jet pump.

IRIS형 방사선검출기 콜리메이터 제작 및 MCNP 코드를 이용한 성능평가 (Development of the IRIS Collimator for the Portable Radiation Detector and Its Performance Evaluation Using the MCNP Code)

  • 지영용;정근호;이완로;최상도;김창종;강문자;박상태
    • 방사성폐기물학회지
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    • 제13권1호
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    • pp.55-61
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    • 2015
  • 방사선검출기를 이용한 고방사성물질의 측정이나 방사선사고 등의 신속한 대응을 위하여 주위의 선량률 준위에 따라 크기별로 여러 종류의 콜리메이터들을 구비해야 하며, 이는 무거운 콜리메이터의 특성상 효율적인 현장 측정에 심각한 장애가 될 수 있다. 본 연구에서는 콜리메이터의 모양을 카메라의 렌즈 조리개 형식으로 제작하여 사용자가 직접 카메라 렌즈를 돌려 초점을 맞추듯이 콜리메이터의 내경을 조절하고 방사선의 감쇄율을 쉽게 알아볼 수 있도록 IRIS형 콜리메이터를 제작하였다. 먼저, 콜리메이터를 위상을 달리한 2 중의 텅스텐 셔터 구조로 제작하여 기계적 공차에 의한 방사선의 침투를 차단하고자 하였다. 그리고 셔터의 재질별로 콜리메이터 내경에 따른 방사선 감쇄율을 MCNP 코드를 이용하여 계산함으로써 이론적인 성능평가를 수행하였다. 계산된 내경의 크기별 감쇄율을 콜리메이터 외부 눈금링에 표시함으로써, 카메라 렌즈에 표시된 배율과 같은 방법으로 사용자가 해당 표시지점으로 콜리메이터 내경을 조절하였을 때, 방사선의 세기가 얼마만 큼 감소되는지 쉽게 알아볼 수 있도록 구현하였다. 끝으로 개발된 IRIS형 콜리메이터를 장착한 소형 방사선검출기를 현장 측정에 활용할 경우, 콜리메이터의 교체 없이 주위 방사선의 세기에 따라 콜리메이터 내경을 적절한 크기로 신속히 교체가 가능하며, 방사선 세기의 감쇄 정도를 쉽게 알아보게 함으로써 신속하고 정확한 대처가 가능할 것으로 판단된다.

FLUID-ELASTIC INSTABILITY OF ROTATED SQUARE TUBE ARRAY IN AN AIR-WATER TWO-PHASE CROSSFLOW

  • CHUNG HEUNG JUNE;CHU IN-CHEOL
    • Nuclear Engineering and Technology
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    • 제38권1호
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    • pp.69-80
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    • 2006
  • Fluid-elastic instability in an air-water two-phase cross-flow has been experimentally investigated using two different arrays of straight tube bundles: normal square (NS) array and rotated square (RS) array tube bundles with the same pitch-to-diameter ratio of 1.633. Experiments have been performed over wide ranges of mass flux and void fraction. The quantitative tube vibration displacement was measured using a pair of strain gages and the detailed orbit of the tube motion was analyzed from high-speed video recordings. The present study provides the flow pattern, detailed tube vibration response, damping ratio, hydrodynamic mass, and the fluid-elastic instability for each tube bundle. Tube vibration characteristics of the RS array tube bundle in the two-phase flow condition were quite different from those of the NS array tube bundle with respect to the vortex shedding induced vibration and the shape of the oval orbit of the tube motion at the fluid-elastic instability as well as the fluid-elastic instability constant.