• 제목/요약/키워드: Nitride fuel

검색결과 31건 처리시간 0.046초

모의 사용후 핵연료를 이용한 질화물 핵연료 소결체 제조 (Fabrication of Nitride Fuel Pellets by Using Simulated Spent Nuclear Fuel)

  • 류호진;이재원;이영우;이정원;박근일
    • 한국분말재료학회지
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    • 제15권2호
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    • pp.87-94
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    • 2008
  • In order to investigate a nitriding process of spent oxide fuel and the subsequent change in thermal properties after nitriding, simulated spent fuel powder was converted into a nitride pellet with simulated fission product elements through a carbothermic reduction process. Nitriding rate of simulated spent fuel was decreased with increasing of the amount of fission products. Contents of Ba and Sr in simulated spent fuel were decreased after the carbothermic reduction process. The thermal conductivity of the nitride pellet was decreased by an addition of fission product element but was higher than that of the oxide fuel containing fission product elements.

고분자전해질 연료전지용 바이폴라 플레이트의 표면형상과 전기적 특성 (Surface Morphology and Electrical Property of PEMFC (Proton Exchange Membrane Fuel Cell) Bipolar Plates)

  • 송연호;윤영훈
    • 한국세라믹학회지
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    • 제45권3호
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    • pp.161-166
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    • 2008
  • The multi-films of a metallic film and a transparent conducting oxide (TCO, indium-tin oxide, ITO) film were formed on the stainless steel 316 and 304 plates by a sputtering method and an E-beam method and then the external metallic region of the stainless steel bipolar plates was converted into the metal nitride films through an annealing process. The multi-film formed on the stainless steel bipolar plates showed the XRD patterns of the typical indium-tin oxide, the metallic phase and the metal substrate and the external nitride film. The XRD pattern of the thin film on the bipolar plates modified showed two metal nitride phases of CrN and $Cr_2N$ compound. Surface microstructural morphology of the multi-film deposited bipolar plates was observed by AFM and FE-SEM. The metal nitride film formed on the stainless steel bipolar plates represented a microstructural morphology of fine columnar grains with 10 nm diameter and 60nm length in FE-SEM images. The electrical resistivity of the stainless steel bipolar plates modified was evaluated.

다층박막 코팅된 PEMFC (Proton Exchange Membrane Fuel Cell)용 바이폴라 플레이트 (Multi-film coated bipolar plates for PEMFC (Proton Exchange Membrane Fuel Cell) application)

  • 전광연;윤영훈;차인수
    • 전력전자학회:학술대회논문집
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    • 전력전자학회 2008년도 하계학술대회 논문집
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    • pp.646-648
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    • 2008
  • The multi-films of a metallic film and a transparent conducting oxide (TCO, indium-tin oxide, ITO) film were formed on the stainless steel 316 and 304 plates by a sputtering method and an E-beam method and then the external metallic region of the stainless steel bipolar plates was converted into the metal nitride films through an annealing process. The multi-film formed on the stainless steel bipolar plates showed the XRD patterns of the typical indium-tin oxide, the metallic phase and the metal substrate and the external nitride film. The XRD pattern of the thin film on the bipolar plates modified showed two metal nitride phases of CrN and $Cr_2N$ compound. Surface microstructural morphology of the multi-film deposited bipolar plates was observed by AFM and FE-SEM. The electrical resistivity of the stainless steel bipolar plates modified was evaluated.

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A study on heat capacity of oxide and nitride nuclear fuels by using Einstein-Debye approximation

  • Eser, E.;Duyuran, B.;Bolukdemir, M.H.;Koc, H.
    • Nuclear Engineering and Technology
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    • 제52권6호
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    • pp.1208-1212
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    • 2020
  • Knowledge on fuel enthalpy and its temperature derivative, the heat capacity, are important quantities in determination of fuel behavior in normal reactor operation and reactor transients. The aim of this study is to compare the heat capacity of oxide and nitrite fuels by using Einstein-Debye approximation. A simple analytical expression was performed to calculate the heat capacity of fuels. To test the validity and reliability, the calculated formulas were compared to published results for various nuclear fuels including UO2, ThO2, PuO2 and UN. Calculated formulas yielded results in consistent with literature.

Dynamic Behavior of Oxide and Nitride LMR Cores during Unprotected Transients

  • Na, Byung-Chan;Dohee Hahn
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1997년도 춘계학술발표회논문집(1)
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    • pp.489-494
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    • 1997
  • A comparative transient analyses were performed for oxide and nitride cores or a large (3000 MWt), pool-type, liquid-metal-cooled reactor (LMR). The study was focused on three representative accident initiators with failure to scram : the unprotected loss-of-flow (ULOF), the unprotected transient overpower (UTOP), and the unprotected fast transient overpower (UFTOP). The margins to fuel melting and sodium boiling have been evaluated for these representative transients. The results show that there is an increase in safety margin with nitride core which maintains the physical dimensions of the oxide core.

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Criticality analysis of pyrochemical reprocessing apparatuses for mixed uranium-plutonium nitride spent nuclear fuel using the MCU-FR and MCNP program codes

  • P.A. Kizub ;A.I. Blokhin ;P.A. Blokhin ;E.F. Mitenkova;N.A. Mosunova ;V.A. Kovrov ;A.V. Shishkin ;Yu.P. Zaikov ;O.R. Rakhmanova
    • Nuclear Engineering and Technology
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    • 제55권3호
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    • pp.1097-1104
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    • 2023
  • A preliminary criticality analysis for novel pyrochemical apparatuses for the reprocessing of mixed uranium-plutonium nitride spent nuclear fuel from the BREST-OD-300 reactor was performed. High-temperature processing apparatuses, "metallization" electrolyzer, refinery remelting apparatus, refining electrolyzer, and "soft" chlorination apparatus are considered in this work. Computational models of apparatuses for two neutron radiation transport codes (MCU-FR and MCNP) were developed and calculations for criticality were completed using the Monte Carlo method. The criticality analysis was performed for different loads of fissile material into the apparatuses including overloading conditions. Various emergency situations were considered, in particular, those associated with water ingress into the chamber of the refinery remelting apparatus. It was revealed that for all the considered computational models nuclear safety rules are satisfied.

폴리스티렌 구형입자를 주형으로 이용한 할로우 메조포러스 질화탄소 구형입자의 합성 (Synthesis of Hollow Mesoporous Carbon Nitride Spheres Using Polystyrene Spheres as Template)

  • 박성수;하창식
    • 접착 및 계면
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    • 제15권2호
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    • pp.63-68
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    • 2014
  • 주형으로 구형의 폴리스티렌을 사용하고 질소와 탄소원으로 시안아미드를 사용하여 열처리 과정을 거친 후 구형의 할로우 메조포러스 질화탄소 물질을 합성하였다. 이때 할로우 메조포러스 질화탄소 물질을 합성하는 과정에서 실리카와 같은 무기물 주형을 사용하지 않기 때문에 이차적인 실리카 제거 공정이 필요 없고 용매를 전혀 사용하지 않는다. 구형의 폴리스티렌 입자는 약 170 nm 크기였고 그리고 할로우 메조포러스 질화탄소 구형입자의 할로우 직경은 약 82 nm, 벽 두께는 약 13 nm이었다. 또한 할로우 메조포러스 질화탄소 물질의 표면적, 나노세공 크기, 세공부피는 각각 $188m^2g^{-1}$, 3.8 nm, $0.35cm^3g^{-1}$이었다. 한편, 할로우 벽은 흑연구조와 유사한 박막층의 쌓임 구조를 가졌으며 이러한 할로우 메조포러스 질화탄소 물질은 연료전지, 촉매, 광촉매, 전자방출 소자 등과 같은 분야에 매우 높은 응용 가능성을 가질 것으로 기대된다.

고분자전해질 연료전지에서 TiN과 Ti/TiN이 코팅된 스텐레스 강 분리판의 부식 특성 (Analysis of Corrosion Characteristics for TiN- and Ti/TiN-coated Stainless Steel Bipolar Plate in PEMFC)

  • 한춘수;채길병;이창래;최대규;심중표
    • Korean Chemical Engineering Research
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    • 제50권1호
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    • pp.118-127
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    • 2012
  • 고분자전해질 연료전지용 분리판 소재로 스텐레스 강의 내식성과 전기전도성을 향상시키기 위해 표면을 TiN(titanium nitride) 또는 Ti/TiN(titanium/titanium nitride)으로 코팅하여 연료전지 운전환경에서 표면 코팅층의 물성 변화를 조사하였다. 200시간의 연료전지 운전에서 표면 코팅층의 부식, 균열(crack), 박리, 표면 화학조성 변화 등을 분석하여 코팅된 TiN 또는 Ti/TiN 박막의 역할을 규명하고자 하였다. 스텐레스 강 분리판의 전기전도도와 부식저항성은 소재 표면에 질화층 박막을 코팅함으로써 증가하였으나 연료전지 환경하에서 운전시 코팅된 박막의 부식과 박리현상이 SUS316L-Ti/TiN을 제외하고 현저히 발생하였다. TiN 코팅층과 하부 기재 사이에 Ti 중간층을 도입함으로써 TiN 박막의 밀착성이 향상되고 또한 코팅층의 두께 증가로 부식 위험성이 감소하는 것을 관찰하였다.