• 제목/요약/키워드: $UO_3$

검색결과 315건 처리시간 0.022초

옥천대(沃川帶) 우라늄광층(鑛層)의 구조규제(構造規制) 및 지구화학적(地球化學的) 특성연구(特性硏究) (Lithologic and Structural Controls and Geochemistry of Uranium Deposition in the Ogcheon Black-Slate Formation)

  • 이대성;윤석규;이종혁;김정택
    • 자원환경지질
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    • 제19권spc호
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    • pp.19-41
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    • 1986
  • Structural, radioactive, petrological, petrochemical, mineralogical and stable isotopic study as well as the review of previous studies of the uranium-bearing slates in the Ogcheon sequence were carried out to examine the lithological and structural controls, and geochemical environment in the uranium deposition in the sequence. And the study was extended to the coal-bearing formation (Jangseong Series-Permian) to compare the geochemical and sedimentologic aspects of uranium chemistry between Ogcheon and Hambaegsan areas. The results obtained are as follows: 1. The uranium mineralization occurs in the carbonaceous black slates of the middle to lower Guryongsan formation and its equivalents in the Ogcheon sequence. In general, two or three uranium-bearing carbonaceous beds are found with about 1 to 1.5km stratigraphic interval and they extend from Chungju to Jinsan for 90km in distance, with intermittent igneous intrusions and structural Jisturbances. Average thickness of the beds ranges from 20 to 1,500m. 2. These carbonaceous slate beds were folded by a strong $F_1$-fold and were refolded by subsequent $F_1$-fold, nearly co-axial with the $F_1$, resulting in a repeated occurrence of similar slate. The carbonaceous beds were swelled in hing zones and were shrinked or thined out in limb by the these foldings. Minor faulting and brecciation of the carbonaceous beds were followed causing metamorphism of these beds and secondary migration and alteration of uranium minerals and their close associations. 3. Uranium-rich zones with high radioactive anomalies are found in Chungju, Deogpyong-Yongyuri, MiwonBoun, Daejeon-Geumsan areas in the range of 500~3,700 cps (corresponds to 0.017~0.087%U). These zones continue along strike of the beds for several tens to a few hundred meters but also discontinue with swelling and pinches at places that should be analogously developed toward underground in their vertical extentions. The drilling surveyings in those area, more than 120 holes, indicate that the depth-frequency to uranium rich bed ranging 40~160 meter is greater. 4. The features that higher radioactive anomalies occur particularly from the carbonaceous beds among the argillaceous lithologic units, are well demonstrated on the cross sections of the lithology and radioactive values of the major uranium deposits in the Ogcheon zone. However, one anomalous radioactive zone is found in a l:ornfels bed in Samgoe, near Daejeon city. This is interpreted as a thermal metamorphic effect by which original uranium contents in the underlying black slate were migrated into the hornfels bed. 5. Principal minerals of the uranium-bearing black slates are quartz, sericite, biotite and chlorite, and as to chemical composition of the black slates, $Al_2O_3$ contents appear to be much lower than the average values by its clarke suggesting that the Changri basin has rather proximal to its source area. 6. The uranium-bearing carbonaceous beds contain minor amounts of phosphorite minerals, pyrite, pyrrhotite and other sulfides but not contain iron oxides. Vanadium. Molybdenum, Barium, Nickel, Zirconium, Lead, Cromium and fixed Carbon, and some other heavy metals appear to be positive by correlative with uranium in their concentrations, suggesting a possibility of their genetic relationships. The estimated pH and Eh of the slate suggests an euxenic marine to organic-rich saline water environment during uranium was deposited in the middle part of Ogcheon zone. 7. The Carboniferous shale of Jangseong Series(Sadong Series) of Permian in Hambaegsan area having low radioactivity and in fluvial to beach deposits is entirely different in geochemical property and depositional environment from the middle part of Ogcheon zone, so-called "Pibanryong-Type Ogcheon Zone". 8. Synthesizing various data obtained by several aspects of research on uranium mineralization in the studied sequence, it is concluded that the processes of uranium deposition were incorporated with rich organic precipitation by which soluble uranyl ions, $U{_2}^{+{+}}$ were organochemically complexed and carried down to the pre-Ogcheon sea bottoms formed in transitional environment, from Red Sea type basin to Black Sea type basin. Decomposition of the organic matter under reducing conditions to hydrogen sulfide, which reduced the $UO{_2}^{+2}$ ions to the insoluble uranium dioxide($UO_2$), on the other side the heavy metals are precipitated as sulfides. 9. The EPMA study on the identification of uraninite and others and the genetic interpretation of uranium bearing slates by isotopic values of this work are given separately by Yun, S. in 1984.

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3 차원 간극 열전도도 모델을 이용한 핵연료봉의 열적 비대칭 거동 해석 (Simulation of Asymmetric Fuel Thermal Behavior Using 3D Gap Conductance Model)

  • 강창학;이성욱;양동열;김효찬;양용식
    • 대한기계학회논문집A
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    • 제39권3호
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    • pp.249-257
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    • 2015
  • 원자력 발전소의 반응로에는 핵분열 에너지를 생성하고 방사성 물질의 유출을 막는 핵연료 집합체가 있으며, 이러한 집합체는 핵연료와 피복관으로 구성되어 있는 핵 연료봉으로 구성되어 있다. 원자로에서 핵연료봉 거동의 안전성을 평가하기 위해 해석적인 방법을 적용하며 이러한 평가 코드를 핵 연료 성능 코드라 한다. 경수로 핵연료 해석에서는 간극의 두께에 따라 열전도도가 크게 영향을 받는 간극 열전도도가 주요 거동해석에 영향을 미친다. 본 연구에서는 간극 두께에 따라 열전도도가 변화하는 3 차원 간극 요소(Gap element)를 제안하였으며, 이를 적용하기 위해 3 차원 열탄성 모듈을 FORTRAN90을 이용하여 개발하였다. 제안된 3 차원 간극 요소를 이용하여 핵 연료봉에서 발생할 수 있는 비대칭적인 형상인 핵 연료 표면에 결함이 생긴 경우 MPS(Missing Pellet Surface)와 핵연료봉의 편심(Eccentricity of the nuclear fuel rod) 형상에 대하여 3 차원 해석을 진행하였다.

Southern hybridization에 의한 질편모충의 유전학적 다양성 (Genetic variance of Tuchomonns uaginclis isolates by Southern hybridization)

  • 류재숙;민득영
    • Parasites, Hosts and Diseases
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    • 제36권3호
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    • pp.207-212
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    • 1998
  • 질편모충 7개 분리주 (국내분리주 UT8, KT6, UT-Kim 및 fr-Lee, 외국 분리주 CDC85, IR78 및 NYH286주)의 유전학적 차이점을 관찰하고자 Southemhybridization을 하였다. 탐침 (probe) 은 질편모충 DNA에 있는 반복적인 염기서열을 기초로 하여 337 bp의 탐침을 제작하였다. 질편모충 각 분리주를 클로닝하고 각각의 원충을 따로 배양하여 DNA를 분리하여 제한효소를 처리한 후 전기영동하고 Southemhybridization을 하였다. 질편모충 분리주에 관계엄이 11개 내외의 븐회이 관찰되었다. 콜로니가 2개 형성된 KT8, IR78 및 KT-Lee 분리주에서는 클로닝하기 전의 분리주와 클로닝하여 형성된 콜로니를 배양한 질편모충에서 같은 bandpattem이 관찰되었다. 사용된 모든 질편모충을 bandpattem에 따라 3군으로 나눌 수 있었는데, KT8 분리주는 국내 분리주인 KT6, KT-Kim 분리주와 같은 band pattern을 보여 1 kb, 1,2 kb, 1.6 kb, 1.9 kb, 2.3 kb, 2.7 kb, 3.2 kb, 3.4 kb, 3.8 kb, 4.9 kb 및 6.0 kb의 11개의 공통 분획을 보였다. 외국분리주로 metronidazole에 내성인 IR78 분리주는 국내 분리주인 fr-Lee 분리주와 같은 분획을 보여 1 kb, 1.2 kb, 1.6 kb, 1.8 kb, 2.1 kb, 2.5 kb, 2.7 kb, 2.9 kb, 3.4 kb, 5.0 kb 및 6.0 kb의 분획을 보였으며 IR78과 같이 약제 내성이 있다고 알려진 CDC85의 경우 IR78, KT-Lee 분리주와 비슷한 분획을 보였으나 2.9 kb가 없고 3.2 kb의 분획이 관찰되었다. 세번째 군에 해당되는 NYH286주는 12개의 분획을 보였는데 IR78, KT-Lee 분리주와 유사한 분획을 보였으나 그 차이점 은 6.0 kb 대신 6.2 kb를, 2. 1 kb 대신 2.0 kb와 2.2 kb를 나타냈다. 이상의 결과로 질편모충 여러 분리주의 유전학적 다양성이 관찰되었다.

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LiCl 용융염 전해환원 공정 희토류원소 산화물의 화학적 거동

  • 박병흥;최인규;정명수;허진목
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2009년도 학술논문요약집
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    • pp.346-346
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    • 2009
  • 산화물 형태 사용후핵연료의 효율적 처분 혹은 재활용을 위한 연구 가운데, 고온의 LiCl 용융염 중에서 전해환원하여 금속으로 환원시킨 후, 환원된 금속을 고온의 LiCl-KCl 용융염에서 전해정련하는 연구가 국내외적으로 활발하게 진행되고 있다. 전해환원을 위해 일정 농도 $Li_2O$가 LiCl 용융염에 첨가되며 $Li_2O$ 농도가 높으면 반응 재질의 부식성이 크게 증가하므로 일반적으로 우라늄 산화물은 1wt% 이하의 $Li_2O$ 농도에서 전해환원 된다. 우라늄 산화물의 전해환원 전위는 $Li_2O$의 전해환원 전위 보다 표준 상태를 기준으로 공정온도인 650 $^{\circ}C$ 에서 약 70 mV 정도 낮기 때문에 전해환원 과정에서 $Li_2O$ 의 환원으로 Li 금속이 생성될 가능성이 있으며 우라늄 산화물은 대부분 직접 전해환원 되지만 일부 Li에 의해 화학적으로 환원되기도 한다. 전해환원 공정에서 환원되지 않은 희토류 산화물은 전해정련 공정에서 $UCl_3$와 반응하여 $UO_2$를 생성시켜 공정 효율을 떨어뜨린다. 따라서 전해환원 공정에서 가능하연 최대한 희토류 산화물을 금속으로 환원시키는 조건을 찾아내는 것이 바람직하고 이를 위해서 우선 전해환원 공정에서 희토류 산화물의 화학적 거동의 이해가 요구된다. 본 연구에서 열역학적 검토를 통하여 희토류 산화물의 환원 조건을 조사한 결과 희토류 산화물은 매운 낮은 $Li_2O$ 농도에서 Li에 의해 환원되고, 1wt% 이하의 $Li_2O$ 농도에서는 Sc와 Lu의 산화물이 $Li_2O$와 복합산화물을 형성하고 이들 복합산화물은 Li에 의해 환원되지 않는 것으로 나타났다. 또한 희토류 원소 별로 희토류 원소 산화물의 Li에 의한 환원 조건으로서 평형상태에서의 $Li_2O$ 농도 즉 환원 임계 $Li_2O$ 농도를 실험적으로 측정하였으며 1wt% $Li_2O$ 농도 이하에서 열역학적 해석과 동일하게 Sc와 Lu만이 복합산화물을 형성하여 Li에 의해 직접환원 되지 않는 것으로 관찰되었다.

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Development of Safeguards System for Advanced Spent Fuel Conditioning Process

  • Lee Tae-Hoon;Song Dae-Yong;Ko Won-Il;Kim Ho-Dong;Jeong Ki-Jeong;Park Seong-Won
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2005년도 춘계 학술대회
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    • pp.426-427
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    • 2005
  • Advanced Spent Fuel Conditioning Process (ACP) is a pyrochemical process in which the spent fuel of PWR is transformed into the uranic metal ingot. Through this process, which has been developed in KAERI since 1998, the radioactivity, the radiotoxicity, the heat and the volume of the PWR spent fuel are reduced by a quarter of the original. To demonstrate a lab-scale process and extract the data for the later pilot-scale process, a demonstration facility of ACP (ACPF) is under construction and the lab-scale demonstration is slated for 2006. To establish the safeguardability of ACPF, a safeguards system including a neutron counter based on non-destructive assay, which is named as ACP Safeguards Neutron Counter (ASNC), the ACP Safeguards Surveillance System (ASSS) which consists of two neutron monitors and five IAEA cameras, and Laser Induced Breakdown System (LIBS) have been developed and are ready to be installed at ACPF. The target materials of ACP to assay with ASNC are categorized into three types among which the first is the uranic metal ingot, the second is the salt waste and the last is $UO_2$ and $U_{3}O_8$ powders, rod cuts and hulls. The Pu content of process nuclear materials can be accounted with ASNC. The ASSS is integrated in the ACP Intelligent Surveillance Software (AISS) in which the IAEA camera images and background signals at the rear doors of ACPF are displayed. The composition of special nuclear materials of ACP can be measured with LIBS which can be a supporting measurement tool for ASNC. The conceptual picture of safeguards system of ACPF is shown in Fig. 1.

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핵의학 이용 방사핵종의 투여후 혈중 $PGE_2$의 변동 (Increased Plasma $PGE_2$ Levels after Administration of Radionuclides Used in Nuclear Medicine)

  • 유용운
    • Journal of Radiation Protection and Research
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    • 제14권1호
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    • pp.8-15
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    • 1989
  • $^{99m}TC,\;^{67}Ga,\;^{131}I,\;^{32}P$각각을 웅성백서에 투여하여 생체에 미치는 혈중 독성의 영향을 측정 비교하였다. 핵종의 투여량은 통상 인체에 주사되는 양을 기준으로하여 조절 하였으며 생화학적 반응 지표로 혈중 BUN, Creatinine, SGOT SGPT와 $PGE_2$의 활성도출 측정하였다. $^{99m}Tc$의 효과로 Creatinine의 변동은 없었으며 BUN, SGOT 및 $PGE_2$활성도가 투여 전에 비하여 증가된 경향을 보였으나 통계적 의의는 없었다. $^{67}Ga,\;^{131}I$$^{32}P$의 경우 BUN, SGPT 및 SGOT 에서의 증가는 임상적 의의는 없었으나 $PGE_2$는 정상치 보다 크게 상승 하였다. 한편 $^{238}U$이 가장 심한 독성을 나타내었다. 따라서 핵의학에서 이용되는 핵종의 방사성 독성의 효과를 평가할 경우 혈중 $PGE_2$의 측정법이 유용할 것으로 생각된다.

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Atomistic simulations of nanocrystalline U0.5Th0.5O2 solid solution under uniaxial tension

  • Xiao, Hongxing;Wang, Xiaomin;Long, Chongsheng;Tian, Xiaofeng;Wang, Hui
    • Nuclear Engineering and Technology
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    • 제49권8호
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    • pp.1733-1739
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    • 2017
  • Molecular dynamics simulations were performed to investigate the uniaxial tensile properties of nanocrystalline $U_{0.5}Th_{0.5}O_2$ solid solution with the Born-Mayer-Huggins potential. The results indicated that the elastic modulus increased linearly with the density relative to a single crystal, but decreased with increasing temperature. The simulated nanocrystalline $U_{0.5}Th_{0.5}O_2$ exhibited a breakdown in the Halle-Petch relation with mean grain size varying from 3.0 nm to 18.0 nm. Moreover, the elastic modulus of $U_{1-y}Th_yO_2$ solid solutions with different content of thorium at 300 K was also studied and the results accorded well with the experimental data available in the literature. In addition, the fracture mode of nanocrystalline $U_{0.5}Th_{0.5}O_2$ was inclined to be ductile because the fracture behavior was preceded by some moderate amount of plastic deformation, which is different from what has been seen earlier in simulations of pure $UO_2$.

경상북도의 문화마을에 대한 문제점 및 개선방향 -어모지구와 무을지구를 중심으로- (Problems and Guidelines for Improvements of Munhwa-Maul with Special Reference to Mueur Munhwa-Maul and Umo Munhwa-Maul(a modern village) in Kyeongbook)

  • 이관희
    • 한국조경학회지
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    • 제26권3호
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    • pp.45-51
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    • 1998
  • This research is concerned with environment problems related to Munhwa-Maul where Korean government are financially much supporting in developing housing sites and constructing houses. The purposes of this research are to find out the problems and to present the practical guidelines in order to improve an environmental quality of Munhwa-Maul in which will be under construction in the near future. The method for finding out the problems are based upon the most atisfaction and dissatisfaction of residents with opened interview. Both Mueur Munhwa-Maul and Umo Munhwa-Maul are considered for this research because Mueur Munhwa-Maul is characterized with a modern village where is located far from the city while Uo Munhwa-Maul, near the city. Also, these Munhwa-Mauls have been firstly constructed. The interview participants are 34 persons in all. They are confined to Mueur Munhwa-Maul and Umo Munhwa Maul that have been firstly constructed in Kyeongook. According to the interviews, each 60% of both Mueur Munhwa-Maul interview participants and Umo Munhwa-Maul ones have shown the their most positive satisfaction in a new housing and facility. It can be seen from that these figures that housing environment including facility of both Munhwa-Mauls is surely improved and successful. On the other hand, 43.8% of Mueur Munhwa-Maul participants and 14% of Umo Munhwa-Maul ones have particularly shown the most negative satisfaction in a size of housing lot. Also, 15.6% of Mueur Munhwa-Maul interview participant and 44% of Umo Munhwa-Maul ones have stated the most dissatisfaction in a traffic convenience. The reasons showing these differences are likely that 90% of Mueur Munhwa-Maul residents are farmer while 85% of Umo Munhwa-Maul ones are not farmer. With this results the purpose of munhwa-Maul project that government has been supporting and the reality of Umo Munhwa-Maul could be never coincident. Therefore, it can be inferred that housing layout should be reconsiderd to be appropriate for agriculture and that the government should carefully consider the contributions of new housing lot to real farmers. In addition, we can say that Munhwa-Maul project should be firstly accomplished in the district far from the city rather than near the city.

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COMPUTATIONAL INVESTIGATION OF 99Mo, 89Sr, AND 131I PRODUCTION RATES IN A SUBCRITICAL UO2(NO3)2 AQUEOUS SOLUTION REACTOR DRIVEN BY A 30-MEV PROTON ACCELERATOR

  • GHOLAMZADEH, Z.;FEGHHI, S.A.H.;MIRVAKILI, S.M.;JOZE-VAZIRI, A.;ALIZADEH, M.
    • Nuclear Engineering and Technology
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    • 제47권7호
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    • pp.875-883
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    • 2015
  • The use of subcritical aqueous homogenous reactors driven by accelerators presents an attractive alternative for producing $^{99}Mo$. In this method, the medical isotope production system itself is used to extract $^{99}Mo$ or other radioisotopes so that there is no need to irradiate common targets. In addition, it can operate at much lower power compared to a traditional reactor to produce the same amount of $^{99}Mo$ by irradiating targets. In this study, the neutronic performance and $^{99}Mo$, $^{89}Sr$, and $^{131}I$ production capacity of a subcritical aqueous homogenous reactor fueled with low-enriched uranyl nitrate was evaluated using the MCNPX code. A proton accelerator with a maximum 30-MeV accelerating power was used to run the subcritical core. The computational results indicate a good potential for the modeled system to produce the radioisotopes under completely safe conditions because of the high negative reactivity coefficients of the modeled core. The results show that application of an optimized beam window material can increase the fission power of the aqueous nitrate fuel up to 80%. This accelerator-based procedure using low enriched uranium nitrate fuel to produce radioisotopes presents a potentially competitive alternative in comparison with the reactor-based or other accelerator-based methods. This system produces ~1,500 Ci/wk (~325 6-day Ci) of $^{99}Mo$ at the end of a cycle.

Dissolution of synthetic U-DBP and corrosion of stainless steel by dissolution schemes

  • Guanghui Wang;Yaorui Li ;Mingjian He ;Meng Zhang ;Yang Gao ;Hui He ;Caishan Jiao
    • Nuclear Engineering and Technology
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    • 제55권5호
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    • pp.1644-1650
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    • 2023
  • In spent fuel reprocessing, UO2(DBP)2 (U-DBP) can be deposited in stainless steel equipment. U-DBP must be removed by dissolution and the process must not cause corrosion to stainless steel. This study was conducted to find the best scheme for dissolution. U-DBP was manufactured by the titrimetric sedimentation method. The effects of different factors on the dissolution of U-DBP were investigated. For example, solid-liquid ratio, hydrazine carbonate solutions with different mass components, mixed solutions containing different concentrations of H2O2, and different carbonates. The results indicated that U-DBP does not have a regular crystal morphology. With the increase of the solid-liquid ratio and the mass fraction of hydrazine carbonate, the concentration of U(VI) at the dissolution equilibrium increases gradually. The addition of H2O2 has a great promotion effect on the dissolution. However, when the concentration of H2O2 is greater than 0.5 M, the dissolution solution may have an erosive effect on the stainless steel. (NH4)2CO3 can increase the dissolution capacity of dissolved U-DBP, but it may also accelerate the corrosion of stainless steel.