• 제목/요약/키워드: $UO_2$ pellet

검색결과 117건 처리시간 0.026초

$UO_2$ 핵연료의 산화거동 (Oxidation Behavior of $UO_2$ Fuel)

  • 강권호;문흥수;나상호;오세용
    • 에너지공학
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    • 제15권1호
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    • pp.8-13
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    • 2006
  • 열중량 분석기와 XRD를 이용하여 $573\sim873K$의 온도범위와 이론밀도의 $94.64\sim99.10%$범위에서 $UO_2$ 핵연료 소결체의 공기 중 산화실험을 수행하였다. XRD를 이용하여 실험온도 범위에서 $UO_2$$U_3O_8$으로 산화되는 것을 확인하였다. 시간에 따른 산화반응은 S자의 형태를 나타내고 있어 핵생성과 성장의 과정을 따르는 것으로 나타났다. 밀도가 증가함에 따라 산화속도는 떨어지고, 산화유도시간은 늘어나는 것으로 나타났다. $UO_2$에서 $U_3O_8$으로의 산화에 대한 활성화 에너지는 $573\sim723K$의 온도범위에서 약 89.54kJ/mol, $723\sim873K$의 온도범위에서는 34.40 kJ/mol로 나타났다.

$Nb_2O_5$ 첨가 $UO_2$ pellet의 수소 분위기와 이산화탄소 분위기 소결 중 미세조직의 형성에 대한 연구 (Microstructure Development during Sintering of $Nb_2O_5$-doped $UO_2$ pellets under $H_2$ and $CO_2$ atmospheres)

  • 송근우;김시형;김봉구;이영우;양명승;박현수
    • Nuclear Engineering and Technology
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    • 제26권4호
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    • pp.484-492
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    • 1994
  • Nb$_2$O$_{5}$가 첨가된 $UO_2$ 소결체의 미세조직을 수소와 이산화탄소 분위기에서 연구하였다. Pellet을 1$700^{\circ}C$ 수소분위기 그리고 130$0^{\circ}C$ 이산화탄소 분위기에서 1-41 시간 동안 소결하였다. Nb$_2$O$_{5}$를 첨가하면 큰 기공들이 형성되고, 이 기공들은 수소분위기에서는 어느정도 수축하지만 이산화탄소 분위기에서는 거의 소멸하지 않는다. 작은 기공들은 수소분위기에서는 거의 전부 소멸되며 이산화탄소 분위기에서는 거의 소멸하지 않는다. 그리고 결정립의 크기도 수소분위기에서 훨씬 증대한다. 따라서 Nb$_2$O$_{5}$ 첨가에 의한 우라늄 확산은 수소분위기에서 훨씬 증가하는 것으로 생각된다. 수소 분위기에서 소결한 Nb$_2$O$_{5}$ 첨가 $UO_2$ pellet의 미세조직을 노내성능의 관점에서 평가하였다. 우라늄 확산의 증가를 설명하기 위해서 Nb$_2$O$_{5}$ 첨가에 의해서 형성 가능한 결함들을 고찰하였다.함들을 고찰하였다.

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핵연료계장을 위한 정밀 드릴링장치 개발 (Development of Precision Drilling Machine for the Instrumentation of Nuclear Fuels)

  • 홍진태;정황영;안성호;정창용
    • 한국정밀공학회지
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    • 제30권2호
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    • pp.223-230
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    • 2013
  • When a new nuclear fuel is developed, an irradiation test needs to be carried out in the research reactor to analyze the performance of the new nuclear fuel. In order to check the performance of a nuclear fuel during the irradiation test in the test loop of a research reactor, sensors need to be attached in and out of the fuel rod and connect them with instrumentation cables to the measuring device located outside of the reactor pool. In particular, to check the temporary temperature change at the center of a nuclear fuel during the irradiation test, a thermocouple should be instrumented at the center of the fuel rod. Therefore, a hole needs to be made at the center of fuel pellet to put in the thermocouple. However, because the hardness and the density of a sintered $UO_2$ pellet are very high, it is difficult to make a small fine hole on a sintered $UO_2$ pellet using a simple drilling machine even though we use a diamond drill bit made by electro deposition. In this study, an automated drilling machine using a CVD diamond drill has been developed to make a fine hole in a fuel pellet without changing tools or breakage of workpiece. A sintered alumina ($Al_2O_3$) block which has a higher hardness than a sintered $UO_2$ pellet is used as a test specimen. Then, it is verified that a precise hole can be drilled off without breakage of the drill bit in a short time.

펠릿과 헐의 분리 연구를 위한 슬리팅 장치 개발 (Development of the slitting device on separation study of pellet and hull)

  • 정재후;윤지섭;홍동희;김영환;진재현;박기용
    • 한국소성가공학회:학술대회논문집
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    • 한국소성가공학회 2003년도 춘계학술대회논문집
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    • pp.236-239
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    • 2003
  • The spent fuel slitting device is an equipment developed in order to feed UO$_2$pellet to the dry pulverizing/mixing device. In this study, we have compared and analyzed the handling method of the slitting and that of the pellet and hull, processing time, separating time for 20kgHM, the number of blades, on the existing slitting device using in DUPIC, and spent fuel management technology research and test facility. Also, we have compared and analyzed about an advantage and weak point, designing and producing, processing, establishment, operation, maintenance about the vertical and horizontal slitting device. Based on these results, we have developed the vertical slitting device. By using the results, we have enhanced the slitting processing time(over 40%)in comparison with DUPIC device, and it will is effectively applied to available data for designing and producing of the hot test facility.

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Properties of Compacts and Pellets Made Using Bimodal- Sized $UO_2$ Powder

  • Kim, Keon-Sik;Song, Kun-Woo;Kang, Ki-Won;Kim, Jong-Hun;Kim, Young-Min
    • Nuclear Engineering and Technology
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    • 제31권6호
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    • pp.608-617
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    • 1999
  • The powder mixture which has a bimodal size distribution, with a large mode corresponding to AUC-UO$_2$ powder and a small one corresponding to ADU-UO$_2$ powder, was prepared, pressed into compacts, and sintered at 1680t for 4 hours in hydrogen gas. The compact density of the powder mixture increases with increasing ADU-UO$_2$content within a content of 20 wt %, since small ADU-UO$_2$ particles can fill interstices between large AUC-UO$_2$particles. The UO$_2$ pellet made using the powder mixture has a lower open porosity than that made using AUC-UO$_2$ powder alone. The mechanism for the formation of a flake-like pore is proposed, and the decrease in open porosity may be ascribed to the decrease in the number of flake-like pores.

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