• 제목/요약/키워드: Thermal Analysis$U_3O_8$ Power

검색결과 2건 처리시간 0.017초

내부 압력변화에 대한 사용후핵연료 분말화장치 가열로의 열 응력 해석 (Thermal Stress Analysis of Spent Fuel Vol-oxidizer Furnace on the Internal Pressure)

  • 김영환;정재후;홍동희;박병석;이종광;윤지섭
    • 한국소성가공학회:학술대회논문집
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    • 한국소성가공학회 2006년도 춘계학술대회 논문집
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    • pp.136-140
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    • 2006
  • We are developing a vol-oxidizer which transforms the spent $UO_2$ pellets into the $U_3O_8$ power through oxidizing process. The vol-oxidizer consists of furnace, filter, heater and valve etc. When the filter is blocked by the powder, the internal pressure of the furnace is increased owing to the air flow restriction. Then, the furnace vessel is swelled and deformed by it. In this paper, we proposed a procedure of the thermal analysis for furnace vessel design of spent fuel vol-oxidizer. In this work, we determined the thickness of the furnace through analyzing the internal pressure and the thermal stress of the furnace with respect to various pressure and temperature. To analyze the thermal stress, we used ANSYS 8.0 for constructing a FEM model of the furnace, and then analyzed it based on the ASME code. We also surveyed the material property and yield stress of SUS304 with various temperature. Analysis results are compared with the yield stress of the material. We manufactured the furnace and conduct the verification experiments.

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사용후핵연료 건식 용기의 단기운영공정 열전달 평가 (ANALYSIS OF HEAT TRANSFER ON SPENT FUEL DRY CASK DURING SHORT-TERM OPERATIONS)

  • 김형진;이동규;강경욱;조천형;권오준
    • 한국전산유체공학회지
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    • 제21권2호
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    • pp.54-61
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    • 2016
  • When spent fuel assemblies from the reactor of nuclear power plants(NPPs) are transported, the assemblies are exposed to short-term operations that can affect the peak cladding temperature of spent fuel assemblies. Therefore, it needs to perform the analysis of heat transfer on spent fuel dry cask during the operation. For 3 dimensional computational fluid dynamnics(CFD) simulation, it is proposed that the short-term operation is divided into three processes: Wet, dry, and vacuum drying condition. The three processes have different heat transfer mode and medium. Metal transportation cask, which is Korea Radioactive Waste Agency(KORAD)'s developing cask, is evaluated by the methods proposed in this work. During working hours, the boiling at wet process does not occur in the cask and the peak cladding temperatures of all processes remain below $400^{\circ}C$. The maximum peak cladding temperature is $173.8^{\circ}C$ at vacuum drying process and the temperature rise of dry, and vacuum drying process occurs steeply.