• Title/Summary/Keyword: 방사성입자

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Heat Transfer and Radiation Shielding Analysis for Optimal Design of Radioisotope Thermoelectric Generator (방사성동위원소 열전 발전기 최적설계를 위한 차폐 및 열전달 해석)

  • Son, Kwang Jae;Hong, Jintae;Yang, Young Soo
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.37 no.12
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    • pp.1567-1572
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    • 2013
  • To supply electric power in certain extreme environments such as a spacecraft or in military applications, a radioisotope thermoelectric generator has been highlighted as a useful energy source owing to its high energy density, long lifetime, and high reliability. A radioisotope thermoelectric generator generates electric power by using the heat energy converted from the radioactive energy of a radioisotope. In this study, FE analyses such as radiation shield analysis, heat transfer analysis, and power recovery rate analysis have been carried out to achieve an optimal design for a radioisotope thermoelectric generator using $SrTiO_2$.

$BaSO_4$ 첨가량에 따른 PET 직물 태에 미치는 영향

  • Gwon, Il-Jun;Park, Seong-Min;Kim, Myeong-Sun;Kim, Sang-Uk;Park, Ji-Yeon;Jang, Yeong-Il;Yeom, Jeong-Hyeon
    • Proceedings of the Korean Society of Dyers and Finishers Conference
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    • 2011.03a
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    • pp.102-102
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    • 2011
  • 레이온 섬유는 dry한 촉감, 고광택, 드레이프성 등 의류 분야에서 요구하는 많은 장점들을 가지고 있으나 타 섬유 소재에 비해 소비량이 적은 것은 합섬이나 면/울 제품에 비해 상대적으로 제품 가격이 높고, 형태안정성이 취약하여 정장 및 캐주얼의 겉감 용도로 쓰기에는 성능 보완이 필요하다. 또한 염색가공 공정에서 구김발생이 많으며, 열고정이 쉽게 이루어지지 않아 습윤강도와 탄성 회복률이 낮아 변형이 쉽게 발생된다. 이에 본 연구에서는 합섬의 장점을 그대로 유지하면서 레이온 섬유가 갖는 고비중과 우수한 드레이프성과 유연한 질감으로 소프트 터치를 발현하는 특수한 레이온 대체 소재를 실현하고자 하였다. 직물에서 드레이프성과 은은한 광택을 확보하기 위해서는 폴리머단계에서 비중과 광택을 발현할 수 있는 무기입자 중 비중이 높고, 중합 후 폴리머 내에서 광택을 유지하는 입자의 선택이 필요한데 본 실험에서는 $BaSO_4$를 이용하여 PET dope액과 중합한 후 용융 방사하여 고비중 폴리에스테르사(100/48)를 제조하였다. 고비중 폴리에스테르사를 이용하여 폭 58inch, 밀도 92T, 중량 324.8g/yd 직물로 제직하여 그에 따른 태를 측정하였다. 태측정기(KES-FB, KATO TECH CO)를 이용하여 인장 & 전단강도, 굽힘강도, 압축강도, 표면측정 시험 결과 $BaSO_4$ 2% 첨가한 원단의 드레이프성이 우수한 것을 확인할 수 있었다.

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Characteristic of PVA-PMAA on the Fixation of Radioactively Contaminated Sand as a Result of a Nuclear Accident (PVA-PMAA에 의한 헥사고 오염모래의 고정화 특성)

  • Won, He-Jun;Ahn, Byung-Kil;Oh, Won-Jun
    • Nuclear Engineering and Technology
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    • v.27 no.1
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    • pp.18-24
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    • 1995
  • Characteristics of poly(vinyl alcohol)-poly(methacrylic acid) system (PVA.-PMAA system) for fixation of radioactive contaminant on sand were studied. Dissociation of carboxyl group in PMAA was found to be suppressed by PVA Permeability of sand layer treated with PVA-PMAA solution is directly proportional to the PMAA concentration when the [PMAA] is below 0.082 M and the empirical proportional constant (k) is -8.95$\times$10 ̄$^4$cm$^{5}$ /mole. The change of permeability can be explained by the formation of an intermacromolecular complex between PVA and PMAA The polymer bridge formed on a sand surface combines sand yams more firmly. The PVA-PMAA system is more effective than the PVA system for the fixation of deposited condensational radionuclides.

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Elemental analysis by neutron induced nuclear reaction - Nuclear track method for the analysis of fissile materials

  • Ha, Yeong-Keong;Pyo, Hyung Yeol;Park, Yong Joon;Jee, Kwang Yong;Kim, Won Ho
    • Analytical Science and Technology
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    • v.18 no.4
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    • pp.263-270
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    • 2005
  • Nuclear track is an useful tool for elemental analysis of radionuclides, such as uranium, plutonium and thorium, etc., and for elements undergoing nuclear reactions with thermal neutrons such as lithium and boron. This method has various application fields such as detecting fissionable radionuelides, measuring the fission rate in nuclear technology, analyzing cosmic radiation from meteorite, calculating the age of minerals as well as their history, etc. Track registration method has been applied to the microscopic analysis of boron and fissionable element such as uranium in KAERI. This report reviews the theoretical background of the nuclear track formation, practical procedures to obtain etched tracks and a perspective of the future.

Decontamination of Uranium-Contaminated Gravel (우라늄으로 오염된 자갈의 제염)

  • Park, Uk Ryang;Kim, Gye Nam;Kim, Seung Soo;Moon, Jei Kwon
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.13 no.1
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    • pp.35-43
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    • 2015
  • A large amount of radioactively-contaminated gravel can be produced on the demolition/restoration of facilities related the back end of fuel cycle. However, because of the lacking in basic knowledge for decontamination of radioactive-contami-nated gravel, this study has performed the basic tests using for soil-washing. To find effective decontamination condition, several experiments were carried out for the selection of optimal decontamination agents. Washing by 0.1 M nitric acid was proved to be more effective than that by distilled water or surfactant for decontamination of uranium-contaminated gravel. In addition, crushing/grinding of uranium-contaminated gravel prior to washing was contributed to increase in of removal efficiency of uranium and reduction of decontamination time. The smaller the sizes of crushed gravel was, the more the removal efficiency increased. Also, small the sized particles improved chances for meeting the clearance requirement of the treated gravel.

Study on the Radioactive Liquid Waste Treatment of Cooling and Decompression Process of Spent Fuel Assembly Cask (사용후핵연료 집합체 캐스크 감온, 감압 공정의 방사성 액체폐기물 처리 대한 연구)

  • 손영준;전용범;김은가;엄성호;권형문;민덕기;양송열;이은표;이형권
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2003.11a
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    • pp.83-89
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    • 2003
  • A temperature- and pressure-reducing process is utilized to handle the spent fuel assembly in the post-irradiation examination facility. This process includes three separated unit processes. First one is the decontamination process to clean the spent fuel assembly casks. The second process is the temperature-reducing process to reduce the temperature elevated by decay process in the spent fuel assembly. The third process is the filtration process to remove insoluble particles existed in the casks using filters. Up-to-date technologies as well as practical theories related to the temperature- and pressure-reducing process is reviewed in this report. The test-operation process for various tests and the test results of the temperature- and pressure-reducing process for J-44 and K-23 spent fuel assemblies are also described in detail. This report must be effectively used for the normal operation of the facility with the awareness of unprecedented problems which could occur by continuing operation of the PIE facility.

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Current Status of X-ray CT Based Non Destructive Characterization of Bentonite as an Engineered Barrier Material (공학적방벽재로서 벤토나이트 거동의 X선 단층촬영 기반 비파괴 특성화 현황)

  • Diaz, Melvin B.;Kim, Joo Yeon;Kim, Kwang Yeom;Lee, Changsoo;Kim, Jin-Seop
    • Tunnel and Underground Space
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    • v.31 no.6
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    • pp.400-414
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    • 2021
  • Under high-level radioactive waste repository conditions, bentonite as an engineered barrier material undergoes thermal, hydrological, mechanical, and chemical processes. We report the applications of X-ray Computed Tomography (CT) imaging technique on the characterization and analysis of bentonite over the past decade to provide a reference of the utilization of this technique and the recent research trends. This overview of the X-ray CT technique applications includes the characterization of the bentonite either in pellets or powder form. X-ray imaging has provided a means to extract grain information at the microscale and identify crack networks responsible for the pellets' heterogeneity. Regarding samples of pellets-powder mixtures under hydration, X-ray CT allowed the identification and monitoring of heterogeneous zones throughout the test. Some results showed how zones with pellets only swell faster compared to others composed of pellets and powder. Moreover, the behavior of fissures between grains and bentonite matrix was observed to change under drying and hydrating conditions, tending to close during the former and open during the latter. The development of specializing software has allowed obtaining strain fields from a sequence of images. In more recent works, X-ray CT technique has served to estimate the dry density, water content, and particle displacement at different testing times. Also, when temperature was added to the hydration process of a sample, CT technology offered a way to observe localized and global density changes over time.

A Model for Evaluating the Radioactive Contamination in the Urban Environment (도시환경에서 방사성물질의 오염평가 모델개발)

  • Hwang, Won-Tae;Kim, Eun-Han;Jeong, Hyo-Joon;Suh, Kyung-Suk;Han, Moon-Hee
    • Journal of Radiation Protection and Research
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    • v.30 no.3
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    • pp.99-105
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    • 2005
  • A model for evaluating radioactive contamination in the urban environment, named METRO-K, was developed as a basic step for accident consequence analysis in case of an accidental release. The three kind of radionuclides $(^{137}Cs,\;^{106}Ru,\;^{131}I)$ and the different chemical forms of iodine (particulate, organic and elemental forms) are considered in the model. The radioactive concentrations are evaluated for the five types of surface (roof, paved road, wall, lawn/soil, tree) as a function of time. Using the model, the contaminative impacts of the surfaces were intensively investigated with respect to with and without precipitation during the measurement periods of radionuclides in air. In addition, a practical application study was conducted using $^{137}Cs$ concentration in air and precipitation measured in an European country at the Chernobyl accident. As a result precipitation was an influential factor in surface contamination. The degree of contamination was strongly dependent on the types of radionuclide and surface. Precipitation was more influential in contamination of $^{137}Cs$ than that of $^{131}I$ (elemental form).

$^{137}Cs$ and $^{90}Sr$ Sorption of Kaolinite (배올리나이트의 $^{137}Cs$$^{90}Sr$ 흡착특성)

  • 정찬호;조영환;박상원;김수진
    • Journal of the Mineralogical Society of Korea
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    • v.7 no.2
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    • pp.91-96
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    • 1994
  • 중.저준위 방사성 폐기물의 대표적인 핵종인 137Cs, 90Sr에 대한 캐올리나이트의 흡착특성을 수용액의 이온강도와 pH의 영양하에서 알아보았다. 흡착실험은 회분식으로 하였고, 사용한 수용액은 NaCl, CaCl2, MgSO4, KCL 각각을 10-1, 10-2, 10-3, 10-4 mole/$\ell$로 하였다. 수용액광물 평형상태의 pH를 4.5, 7.0, 10.5로 조절하였다. 실험결과 캐올리나이트의 Cs, Sr 흡착은 이온강도와 pH에 상당한 영향을 받으며, Sr 흡차에 양이온들의 경쟁은 Ca2+ Mg2+>K+>Na+ 순을 보이고, Cs의 경우에는 K+>Ca2+ Mg2+>Na+의 순을 보인다. 이는 수용액상에서 이온들의 수호에너지와 관련되며, 광물입자와 이온들의 물구조변환특성에 의해 설명된다. Cs과 Sr 사이에 흡착우선성은 산성 내지 약알카리에서는 Cs이 Sr보다 흡착이 잘 되나, 강알칼리성 환경에서는 Sr이 Cs보다 흡착이 잘 되는 pH 의존성을 보였다. 수용액의 pH가 증가함에 따라 핵종의 흡착량이 증가하는데, 이는 캐올리나이트의 흡착자리인 실라놀과 알루미놀에 의한 제타전위가 pH에 의존함과 잘 일치한다.

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Investigation of the Radiative Heating from Aircraft Plume with Particles (입자에 의한 항공기 플룸의 열복사 가열에 관한 연구)

  • Go, Gun-Yung;Yi, Kyung-Joo;Lee, Sung-Nam;Kim, Won-Cheol;Baek, Seung-Wook;Kim, Man-Young
    • Journal of the Korean Society for Aeronautical & Space Sciences
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    • v.40 no.9
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    • pp.737-744
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    • 2012
  • The finite volume method for radiation is applied for the analysis of radiative base heating by SE and PE of the aircraft exhaust plume. The exhaust plume is considered as an absorbing, emitting, and scattering medium, while the base plane is assumed to be cold and black. The radiative properties of non-gray gases are obtained through the WSGGM, and the particle is modelled as spheres. The present method is validated by comparing the results with those of the backward Monte-Carlo method and then the radiative base heating characteristics are analyzed by changing such various parameters as particle concentration, temperature, and scattering phase function. The results show that the radiative heat flux coming into the base plane decreases with altitude and distance, but it increases as the particle temperature increases. The forward scattering of particles increases PE while it decreases SE.