• 제목/요약/키워드: UO2

검색결과 620건 처리시간 0.029초

Study of the Changes in Composition of Ammonium Diuranate with Progress of Precipitation, and Study of the Properties of Ammonium Diuranate and its Subsequent Products Produced from both Uranyl Nitrate and Uranyl Fluoride Solutions

  • Manna, Subhankar;Kumar, Raj;Satpati, Santosh K.;Roy, Saswati B.;Joshi, Jyeshtharaj B.
    • Nuclear Engineering and Technology
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    • 제49권3호
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    • pp.541-548
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    • 2017
  • Uranium metal used for fabrication of fuel for research reactors in India is generally produced by magnesio-thermic reduction of $UF_4$. Performance of magnesio-thermic reaction and recovery and quality of uranium largely depends on properties of $UF_4$. As ammonium diuranate (ADU) is first product in powder form in the process flow-sheet, properties of $UF_4$ depend on properties of ADU. ADU is generally produced from uranyl nitrate solution (UNS) for natural uranium metal production and from uranyl fluoride solution (UFS) for low enriched uranium metal production. In present paper, ADU has been produced via both the routes. Variation of uranium recovery and crystal structure and composition of ADU with progress in precipitation reaction has been studied with special attention on first appearance of the precipitate Further, ADU produced by two routes have been calcined to $UO_3$, then reduced to $UO_2$ and hydroflorinated to $UF_4$. Effect of two different process routes of ADU precipitation on the characteristics of ADU, $UO_3$, $UO_2$ and $UF_4$ were studied here.

COMPARISON OF NEUTRONIC BEHAVIOR OF UO2, (TH-233U)O2 AND (TH-235U)O2 FUELS IN A TYPICAL HEAVY WATER REACTOR

  • MIRVAKILI, SEYED MOHAMMAD;KAVAFSHARY, MASOOMEH ALIZADEH;VAZIRI, ATIYEH JOZE
    • Nuclear Engineering and Technology
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    • 제47권3호
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    • pp.315-322
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    • 2015
  • The research carried out on thorium-based fuels indicates that these fuels can be considered as economic alternatives with improved physical properties and proliferation resistance issues. In the current study, neutronic assessment of $UO_2$ in comparison with two $(Th-^{233}U)O_2$, and $(Th-^{235}U)O_2$ thorium-based fuel loads in a heavy water research reactor has been proposed. The obtained computational data showed both thorium-based fuels caused less negative temperature reactivity coefficients for the modeled research reactor in comparison with $UO_2$ fuel loading. By contrast, $^{235}U$-containing thorium-based fuel and $^{235}U$-containing thorium-based fuel loadings in the thermal core did not drastically reduce the effective delayed neutron fractions and delayed neutron fractions compared to $UO_2$ fuel. A provided higher conversion factor and lower transuranic production in the research core fed by the thorium-based fuels make the fuel favorable in achieving higher cycle length and less dangerous and costly nuclear disposals.

UO$_2$(NO$_3$)$_2$ 용액으로부터 Ammonium Uranyl Carbonate 제조 (A Precipitation of Ammonium Uranyl Carbonate from Uranylnitrate Solution)

  • 김응호;김형수;이규암;유재형;최청송
    • 한국세라믹학회지
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    • 제35권6호
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    • pp.559-568
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    • 1998
  • Studies of preparation condition and characteristics of AUC(ammonium uranyl carbonate) were carried out to optimize AUC process with different reactor sizes and precipitation methos. As results four types of precipitates with different chemical compositions and morphologies were obtained from the reaction of {{{{ {(NH }_{4 }) { }_{2 } {CO }_{3 } }} with {{{{ {UO }_{2 }( {NO }_{3 }) { }_{2 } }} solution. A phase diagram has been made and crystal structure and chemical composition of each phase have been characterized by using SEM X-ray IR and thermal analysis. It was found that ammonium uranyl carbonate {{{{ {(NH }_{4 }) { }_{4 } {UO }_{2 } {(CO }_{3 }) { }_{3 } }} with monoclinic crystal morphology could be syn-thesized when the mole ratio of in {{{{ {(NH }_{4 }) { }_{2 } {CO }_{3 }/ {UO }_{2 } {(NO }_{3 }) { }_{2 } }} in the solution was higher than 5 Also a mechanism and a precipitating condition on rounding of the AUC particle were examined in the course of the AUC pre-cipitation. The rounding of the AUC particle was possible only by external circulation using pump not by internal circulation using agitator.

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변형 Sol-Gel 방법을 이용한 고온가스로 핵연료 미세구입자 제조 (HTGR Nuclear Fuel Microsphere Preparation Using the Modified Sol-Gel Method)

  • 정경채;김연구;오승철;조문성
    • 한국세라믹학회지
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    • 제46권6호
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    • pp.574-582
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    • 2009
  • $UO_2$ microsphere particles, core material of HTGR(High Temperature Gas Reactor) nuclear fuel, were prepared using by the GSP(Gel Supported Precipitation) method which is a modified-method of the wet sol-gel process. The spherical shape of initial liquid ADU droplets from the vibration nozzle system was continuously kept till the conversion to the final $UO_2$ microsphere. But the size of a final $UO_2$ microsphere was shrunken to about 25% of an initial ADU droplet size. Also, we found that the composition of dried-ADU gel particles was constituted of the very complicated phases, coexisted the U=O, C-H, N-H, N-O, and O-H functional groups by FT-IR. The important factors for obtain the no-crack $UO_2$ microsphere during the thermal treatment processes must perfectly wash out the remained-$NH_4NO_3$ within the ADU gel particle in washing process and the selections of an appropriate heating rate at a suitable gas atmosphere, during the calcining of ADU gel particles, the reducing of $UO_3$ particles, and the sintering of $UO_2$ particles, respectively.

사고저항성 핵연료용 세라믹 미소셀 UO2 소결체의 Cs 포집반응에 대한 열역학적 평가 (Thermodynamic Evaluations of Cesium Capturing Reaction in Ceramic Microcell UO2 Pellet for Accident-tolerant Fuel)

  • 전상채;김건식;김동주;김동석;김종헌;윤지해;양재호
    • 방사성폐기물학회지
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    • 제17권1호
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    • pp.37-46
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    • 2019
  • 사고저항성 핵연료의 일환으로 $UO_2$ 입자가 세라믹 셀 벽으로 둘러싸인 미세구조를 갖는 세라믹 미소셀 $UO_2$ 소결체를 개발 중이다. 이는 핵분열생성물들을 $UO_2$ 펠렛 내에 포집하여 펠렛 외부로의 방출을 저감함으로써 봉내압 상승을 완화하고 응력부식균열 발생률을 낮춘다. 생성량이나 방사능 측면에서 위험한 핵분열생성물 중 하나로 여겨지는 세슘은 세라믹 미소셀소결체 내에서 셀 물질과 화학반응 하여 포집될 수 있다. 따라서, 세슘 포집능은 해당 화학반응의 열역학적, 속도론적 특성에 의해 결정된다. 역으로, 미소셀 소결체의 조성설계 시 해당 반응에 대한 열역학적 예측이 필수적이다. 본 연구는 세라믹 현재 개발 중인 여러 미소셀 조성(Si-Ti-O, Si-Cr-O, Si-Al-O)에 대해 세슘의 포집능을 평가하는 열역학적 계산을 다룬다. 계산에 앞서 먼저 HSC Chemistry를 이용해 세슘과 셀 물질의 물리/화학적 상태를 정의한 후, LWR 정상운전 모사환경에서 계산된 세슘포텐셜(${\Delta}G_{Cs}$)과 산소포텐셜(${\Delta}G_{O_2}$)에 근거하여 세슘포집 반응성을 평가하였다. 계산 결과에 근거하면, 세슘 포집반응은 상기 모든 조성에서 자발적일 것으로 예상되며 이로써 조성설계의 근거를 제시함과 동시에 세슘의 포집능을 평가하는 효과적인 방법을 제공한다.

Effect of a Li2O Additive on the Sintering Behavior of UO2 in the H2 and CO2 Atmospheres

  • Kim, Si-Hyung;Joung, Chang-Young;Kim, Yeon-Gu;Lee, Soo-Chul;Kim, Ban-Soo;Na, Sang-Ho;Lee, Young-Woo;Suhr, Dong-Soo
    • 한국세라믹학회지
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    • 제41권8호
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    • pp.567-572
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    • 2004
  • The variation of the sintered density and grain size of UO$_2$ as a function of the Li$_2$O amount and sintering atmosphere was observed. Li$_2$O enhanced the grain growth of the UO$_2$ pellet in H$_2$, but rather hindered it in $CO_2$ atmosphere. Grain size of the UO$_2$ and UO$_2$-0.1 wt%Li$_2$O pellets was, respectively, 8 $\mu$m and 100 $\mu$m at 168$0^{\circ}C$ in the H$_2$ atmosphere, and that of each pellet was, respectively, 24 $\mu$m and 17 $\mu$m at the same temperature in the $CO_2$ atmosphere. As-received Li$_2$O powder, which had been composed of Li$_2$O and LiOH, was converted to the Li$_2$CO$_3$ phase after heating to 80$0^{\circ}C$ in $CO_2$. On the other hand, the Li$_2$O and LiOH phases remained unchanged in H$_2$ atmosphere. In the H$_2$, the as-received Li$_2$O powder began to evaporate at about 105$0^{\circ}C$ and then about 20 wt% residue was left at 150$0^{\circ}C$. But, most of the Li elements evaporated at 150$0^{\circ}C$ in the $CO_2$ atmosphere.

Surface Complexation Modeling of $UO_2^{2+}$Sorption onto Goethite and Kaolinite

  • Jinho Jung;Jae kwang lee;Cho, Yong-Hwan;Dong kwon Keum;Hahn, Pil-Soo
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1998년도 춘계학술발표회논문집(2)
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    • pp.453-457
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    • 1998
  • The sorption of UO$_2$$^{2+}$showed ionic strength independece for goethite and dependence for kaolinite. In the presence of carbonate, the sorption decreased in the weakly alkaline pH range becase of the formation of aqueous U(VI)-carbonate complexes. The sorption of UO$_2$$^{2+}$onto goethite and kaolinite under various experimental conditions was successfully interpreted using a surface complexation modeling, named triple layer model (TLM). The best fit to the experimental data was obtained by the FITEQL program, and then evaluated with available spectroscopic data. The results showed the versatility of surface complexation modeling over empirical one to predict UO$_2$$^{2+}$ sorption behavior.avior.

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