• Title, Summary, Keyword: ${U_3}{O_8}$

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5kg $U_{3}O_{8}$ Batch Scale Mock-up Test for the Electrochemical Reduction of Spent Oxide Fuel (사용후핵연료의 전기화학적 금속전환을 위한 5kg $U_{3}O_{8}$ Batch 규모의 Mock-up 시험)

  • 오승철;허진목;홍순석;이원경;서중석;박승원
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.1 no.1
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    • pp.47-53
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    • 2003
  • An electrochemical reduction technology which can reduce the decay heat, volume, and radioactivity of spent fuel by a factor of quarter through converting oxide type spent fuel to a metallic form in a molten salt was developed and tests in a scale of g (3- 40g $U_{3}O_{8}$ batch) have been carried out by Korea Atomic Energy Research Institute. In this research, the reaction apparatus in a scale of 5kg $U_{3}O_{8}$ batch was designed and manufactured for the mock-up test to obtain design data of the apparatus which will be used for the hot test in a scale of 20kg $U_{3}O_{8}$ batch. The electrochemical reduction behavior of $U_{3}O_{8}$ was analyzed regarding the operational factors and fresh $U_{3}O_{8}$ powder was metallized with a more than 99% yield verifying the process validity of electrochemical reduction process in a kg scale.

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Effect of $TiO_2$ on Sintering Behavior of Mixed $UO_2$ and $U_3O_8$ Powder Compacts

  • Song, Kun-Woo;Kim, Keon-Sik;Kang, Ki-Won;Kim, Young-Min;Yang, Jae-Ho;Jung, Youn-Ho
    • Nuclear Engineering and Technology
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    • v.31 no.5
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    • pp.455-464
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    • 1999
  • The effect of TiO$_2$ on the sintering behavior of mixed UO$_2$-U$_3$O$_{8}$ Powder compacts has been investigated using the U$_{3}$O$_{8}$ powder made tv oxidation of defective UO$_{2}$ pellets. Without TiO$_2$, UO$_2$ pellet density is inversely proportional to U$_3$O$_{8}$ content and is below 94 %TD in the U$_3$O$_{8}$ range above 15 wt%. Using more than 0.1 wt % TiO$_2$, however, the density decreases slightly with U$_3$O$_{8}$ content and thus is higher than about 94% TD in the whole range of U$_3$O$_{8}$ content. The grain sizes of UO$_2$ pellets with more than 0.1 wt % TiO$_2$are larger than about 30${\mu}{\textrm}{m}$. Therefore, the U$_3$O$_{8}$ Powder can be reused without any restriction on its amount in UO$_2$ pellet fabrication by sintering the mixed UO$_2$-U$_3$O$_{8}$ compact with the aid of TiO$_2$. Mechanisms for densification and grain growth are proposed and discussed, based on a dilatometry study and an examination of microstructure. microstructure.

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RECYCLING PROCESS OF U3O8 POWDER IN MnO-Al2O3 DOPED LARGE GRAIN UO2 PELLETS

  • Oh, Jang Soo;Kim, Dong-Joo;Yang, Jae Ho;Kim, Keon Sik;Rhee, Young Woo;Koo, Yang-Hyun
    • Nuclear Engineering and Technology
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    • v.46 no.1
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    • pp.117-124
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    • 2014
  • The effect of various process variables on the powder properties of recycled $U_3O_8$ from MnO-$Al_2O_3$ doped large grain $UO_2$ pellets and the effect of those recycled $U_3O_8$ powders on the sintered density and grain size of MnO-$Al_2O_3$ doped large grain $UO_2$ pellets have been investigated. The evolution of morphology, size, and BET surface area of the recycled $U_3O_8$ powders according to the respective variation of the thermo-mechanical treatment variables of oxidation temperature, powder milling, and sequential cyclic heat treatment of oxidation and then reduction was examined. The correlation between the BET surface area of recycled $U_3O_8$ powder and the sintered pellet properties of MnO-$Al_2O_3$ doped pellets showed that the pellet density and grain size of doped pellets were increased and then saturated by increasing the BET surface area of the recycled $U_3O_8$ powder. The density and grain size of the pellets were maximized when the BET surface area of the recycled $U_3O_8$ powder was in the vicinity of $3m^2/g$. Among the process variables applied in this study, the cyclic heat treatment followed by low temperature oxidation was a potential process combination to obtain the sinter-active $U_3O_8$ powder.

The High Temperature Oxidation Behavior of l0wt%$Gd_2 O_3$- Doped $UO_2$

  • J.H. Yang;K.W. Kang;Kim, K.S.;K.W. Song;Kim, J.H.
    • Nuclear Engineering and Technology
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    • v.33 no.3
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    • pp.307-314
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    • 2001
  • The changes of weight gain, structure, morphology and uranium oxidation states in l0wt% G $d_2$ $O_3$-doped U $O_2$ during the oxidation below 475$^{\circ}C$ and heat treatment at 130$0^{\circ}C$ in air were investigated using TGA, XRD, SEM, EPMA and XPS. The room temperature ( $U_{0.86}$G $d_{0.14}$) $O_2$Cubic Phase Converted to highly distorted ( $U_{0.86}$G $d_{0.14}$)$_3$ $O_{8}$ -type sing1e Phase by oxidation at 475 $^{\circ}C$ in air. This oxidized phase was reduced by annealing at 130$0^{\circ}C$ in air. The room temperature XRD pattern of the 130$0^{\circ}C$ annealed powder revealed that ( $U_{0.86}$G $d_{0.14}$)$_3$ $O_{8}$ -type single phase was separated into Gd-depleted $U_3$ $O_{8}$ and Gd-enriched ( $U_{0.7}$G $d_{0.3}$) $O_2$$_{+x}$ type cubic phase. The reduction and phase separation by the high temperature annealing of kinetically metastable and highly deformed ( $U_{0.86}$G $d_{0.14}$)$_3$ $O_{8}$ -type phase are interpreted in terms of cation size difference between G $d^3$$^{+}$ and U according to the oxidation state of U.U.U.U.U.te of U.U.U.U.U.

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5kg $U_3O_8$/Batch Scale Mock-up Test for the Electrochemical Reduction of Spent Oxide Fuel (사용후핵연료의 전기화학적 금속전환을 위한 5kg $U_3O_8$/Batch 규모의 Mock-up시험)

  • 오승철;허진목;홍순석;이원경;서중석;박성원
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • pp.358-362
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    • 2003
  • An electrochemical reduction technology which can reduce the decay heat, volume, and radioactivity of spent fuel by a factor of quarter by converting oxide type spent fuel to a metallic form in a molten salt was developed and mock-up test in a 5kg $U_3O_8$/batch scale was carried out. The electrochemical reaction was analyzed regarding the operational factors. The research efforts was also concentrated on the apparatus development for a hot test. Fresh $U_3O_8$ powder was metallized with a more than 99% yield via this electrochemical technology and design data for the 20kg $U_3O_8$/batch scale apparatus were also obtained.

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Sulfurization Reaction Characteristics of Eu-doped Uranium Oxides (유로퓸 고용(固溶) 우라늄산화물(酸化物)의 황화반응(黃化反應) 특성(特性))

  • Lee, Jae Won;Park, Geun Il;Lee, Jung Won
    • Resources Recycling
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    • v.22 no.3
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    • pp.57-64
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    • 2013
  • Sulfurization reaction characteristics of $Eu_2O_3$, uranium oxides($UO_2$, $U_3O_8$), mixture of $Eu_2O_3$ and uranium oxides, Eu-doped uranium oxides($(U,Eu)O_2$, $(U,Eu)_3O_8$), and phase-separated products prepared by HOX (High temperature OXidation) of $(U,Eu)O_2$ were investigated in the temperature range from 400 to $800^{\circ}C$. Only $Eu_2O_3$ in the mixture of $Eu_2O_3$ and uranium oxides was converted into $Eu_3S_4$ by sulfurization reaction at $450^{\circ}C$ without reaction between them. Sulfurization reaction behavior of $(U,Eu)_3O_8$ and $(U,Eu)O_2$ up to $600^{\circ}C$ was similar to $U_3O_8$ and $UO_2$, respectively, while they were sulfurized into Eu-rich $(U,Eu)S_x$ and ${\alpha}-US_2$ at $800^{\circ}C$. In the sulfurization of RE-rich $(U,Eu)_4O_9$ and $U_3O_8$ prepared by high temperature oxidation, it was confirmed that RE-rich $(U,Eu)S_x$ and UOS phases were formed at $600^{\circ}C$. For Eu-rich $(U,Eu)O_2$ and $UO_2$ prepared by reduction of HOX products, it was identified that Eu-rich (U,Eu)OS was formed at $450^{\circ}C$ by sulfurization of Eu-rich $(U,Eu)O_2$, while $UO_2$ remained unreacted.

공기 유량의 시간 변화에 따른 $U_3O_8$ 타원입자에 대한 거동 특성 해석

  • Kim, Yeong-Hwan;Jeong, Jae-Hu;Lee, Hyo-Jik;Park, Byeong-Seok;Yun, Ji-Seop
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • pp.305-306
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    • 2007
  • ACP(Advanced Spent Fuel Conditioning Process)의 금속전환로에 $U_3O_8$을 공급하기 위하여 20 kgHM/batch의 $UO_2$ 펠릿(pellets)을 처리할 수 있는 건식분말화 장치가 개발되고있다. 건식분말화 장치는 500 $^{\circ}C$온도에서 공기를 공급하여 일정한 입도범위의 균질한 $U_3O_8$을 만든다. 이런 건식 분말화 장치의 효율을 높이기 위해서는 반웅로에 불어 넣어주는 공기의 유량을 증가시킬 필요가 있다. 하지만 공기와 반응하여 생성되는 $U_3O_8$ 입자는 그 크기가 최소 3 ${\mu}$m 정도로 매우 미세하여,반응로 출구를 통해 외부로 빠져나갈 가능성 이있다. 이를 방지하기 위해 분말화 장치 출구 바깥에는 필터가 설치되어 있으나 공기와 함께 $U_3O_8$ 입자가 계속해서 빠져 나갈 경우 입자로 인해 필터가 막혀 제 기능을 할 수 없게 된다. 따라서 건식 분말화 장치는 미세한 $U_3O_8$ 입자가 반응로 밖으로 빠져나가지 않도록 입구에서의 공기 유량을 일정 수준 이하로 조절해주는 것이 필요하다. 이 연구의 목적은 초기 유량으로부터 유량을 점점 증가시키면서 시간변화에 따른 입자 거동 특성을 해석하며, 결과로부터 주어진 크기의 타원입자에 대해 최대 허용 공기 유량을 결정하고자한다. 이 해석을 위해 유동과 입자를 동시에 해석할 수 있는 ANSYS-CFX 5.7.1과 ANSYS-CFX 10.0 두 가지의 소프트웨어가 사용되었다. 해석 결과를 바탕으로 좀더 정확한 유량 한계치 계산을 위해 추가로 수행되어야 할 해석에 대해 제안하였다.

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Phase Separation of Gd-doped UO2 and Measurement of Gd Content Dissolved in Uranium Oxide (Gd-doped UO2의 상분리 및 UO2에 고용된 Gd 함량 측정)

  • 김건식;양재호;송근우;김길무
    • Journal of the Korean Ceramic Society
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    • v.40 no.9
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    • pp.916-920
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    • 2003
  • The change of structure and morphology in ( $U_{0.913}$G $d_{0.087}$) $O_2$ during oxidation at 475$^{\circ}C$ and heat treatment at 130$0^{\circ}C$ in air were investigated using XRD, SEM, and EPMA. The ( $U_{0.913}$G $d_{0.087}$) $O_2$ cubic phase converted to ( $U_{0.913}$G $d_{0.087}$)$_3$ $O_{8}$ orthorhombic phase by oxidation at 475$^{\circ}C$ in air. The XRD and EPMA result of the 130$0^{\circ}C$ heat treated powder revealed that ( $U_{0.913}$G $d_{0.087}$)$_3$ $O_{8}$ orthorhombic phase was separated into $U_3$ $O_{8}$ and ( $U_{0.67}$G $d_{0.33}$) $O_{2+}$x/ cubic phase. The weight variations of (U,Gd) $O_2$ with various Gd contents were measured using TGA at the same heat treated condition. The weight variation during the heat treatment of Gd dissolve (U,Gd) $O_2$ in air can be expressed in terms of phase reaction equations related with oxidation and phase separation. Based on these phase reaction, a initial content of Gd dissolved in (U,Gd) $O_2$ can be exactly calculated by measuring the weight change during the heat treatment.

Measurement of Terminal Velocity for Scatter Prevention of Powder in the Voloxidizer for Oxidation of UO$_{2}$ Pellet (UO$_{2}$ 펠릿 산화로의 분말 비산 방지를 위한 최종속도 측정)

  • Kim Young-Hwan;Yoon Ji-Sup;Jung Jae-Hoo;Jin Jae-Hyun;Hong Dong-Hee
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.3 no.2
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    • pp.77-84
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    • 2005
  • A voloxidizer for a hot cell demonstration, that handles spent fuels of a high radiation level in a limited space should be small and spent fuel powders should not be dispersed out of the equipment involved. In this study a density rate equation as well as the Stokes'equation has been proposed in order to obtain the theoretical terminal velocity of powders. The terminal velocity of U$_{3}$O$_{8}$ has been predicted by using the terminal velocity of SiO$_{2}$, and then determination has been the optimum air flow rate which is able to prevent powders from scattering. An equation which has shown a relationship between theoretical terminal velocities of U$_{3}$O$_{8}$ and SiO$_{2}$ has been derived with the help of the Stokes'equation, and then an experimental verification made for the theoretical Stokes' equation of SiO$_{2}$ by means of an experimental device made of acryl. The theoretical terminal velocity based on the proposed density rate equation has been verified by detecting U$_{3}$O$_{8}$ powders in a filter installed in the mock-up voloxidizer. As the results, the optimum air flow rates seem to be 20 LPM by the Stokes'equation while they are 14.5 L/min by the density rate equation. At the experiments with the mock-up voloxidizer, a trace amount of U$_{3}$O$_{8}$ seems to be detectable at the air flow rate of 14.5 L/min by the density rate equation, but U$_{3}$O$_{8}$ powders of 7$\mu$m diameter seem detectable at the air flow rate of 20 L/min by the Stokes'equation. It is revealed that 14.5 L/min is the optimum air flowe rate which is capable of preventing U$_{3}$O$_{8}$ powders from scattering in the UO$_{2}$ voloxidizer and the proposed density rate equation is proper to calculate the terminal velocity of U$_{3}$O$_{8}$ powders.

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