• 제목/요약/키워드: UO2

검색결과 620건 처리시간 0.026초

Spontaneous Steam Explosions Observed In The Fuel Coolant Interaction Experiments Using Reactor Materials

  • Jinho Song;Park, Ikkyu;Yongseung Sin;Kim, Jonghwan;Seongwan Hong;Byungtae Min;Kim, Heedong
    • Nuclear Engineering and Technology
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    • 제34권4호
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    • pp.344-357
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    • 2002
  • The present paper reports spontaneous steam explosions observed in fuel coolant interaction experiments using prototypic reactor materials. Pure ZrO$_2$ and a mixture of UO$_2$ and ZrO$_2$ are used. A high temperature molten material in the form of a jet is poured into a subcooled water pool located in a pressure vessel. An induction skull melting technique is used for the melting of the reactor material. In both tests using pure ZrO$_2$ and a mixture of UO$_2$ and ZrO$_2$, either a quenching or a spontaneous steam explosion was observed. The morphology of debris and pressure profile clearly indicate the differences between the qunching cases and explosion cases. The dynamic pressure. dynamic impulse, water temperature, melt temperature, and static pressure Inside the containment chamber were measured . As the spontaneous steam explosion for the reactor material is firstly observed in the present experiments, the results of present experiments could be a siginificant step forward the understanding the explosion of the reactor material.

CORE DESIGN FOR HETEROGENEOUS THORIUM FUEL ASSEMBLIES FOR PWR(1)-NUCLEAR DESIGN AND FUEL CYCLE ECONOMY

  • BAE KANG-MOK;KIM MYUNG-HYUN
    • Nuclear Engineering and Technology
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    • 제37권1호
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    • pp.91-100
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    • 2005
  • Kyung-hee Thorium Fuel (KTF), a heterogeneous thorium-based seed and blanket design concept for pressurized light water reactors, is being studied as an alternative to enhance proliferation resistance and fuel cycle economics of PWRs. The proliferation resistance characteristics of the KTF assembly design were evaluated through parametric studies using neutronic performance indices such as Bare Critical Mass (BCM), Spontaneous Neutron Source rate (SNS), Thermal Generation rate (TG), and Radio-Toxicity. Also, Fissile Economic Index (FEI), a new index for gauging fuel cycle economy, was suggested and applied to optimize the KTF design. A core loaded with optimized KTF assemblies with a seed-to-blanket ratio of 1: 1 was tested at the Korea Next Generation Reactor (KNGR), ARP-1400. Core design characteristics for cycle length, power distribution, and power peaking were evaluated by HELIOS and MASTER code systems for nine reload cycles. The core calculation results show that the KTF assembly design has nearly the same neutronic performance as those of a conventional $UO_2$ fuel assembly. However, the power peaking factor is relatively higher than that of conventional PWRs as the maximum Fq is 2.69 at the M$9^{th}$ equilibrium cycle while the design limit is 2.58. In order to assess the economic potential of a heterogeneous thorium fuel core, the front-end fuel cycle costs as well as the spent fuel disposal costs were compared with those of a reference PWR fueled with $UO_2$. In the case of comprising back-end fuel cycle cost, the fuel cycle cost of APR-1400 with a KTF assembly is 4.99 mills/KWe-yr, which is lower than that (5.23 mills/KWe-yr) of a conventional PWR. Proliferation resistance potential, BCM, SNS, and TG of a heterogeneous thorium-fueled core are much higher than those of the $UO_2$ core. The once-through fuel cycle application of heterogeneous thorium fuel assemblies demonstrated good competitiveness relative to $UO_2$ in terms of economics.

UO2 및 (U1-yCey)O2 소결체의 열팽창 측정 및 평가 (The Linear Thermal Expansion Measurements and Estimations for UO2 and (U1-yCey)O2 Pellet)

  • 김동주;김용수;이영우
    • 한국세라믹학회지
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    • 제42권5호
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    • pp.346-351
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    • 2005
  • The linear thermal expansions of $UO_2$ and $(U_{1-y}Ce_y)O_2$ pellet were measured from room temperature to $1400^{\circ}C$ as a function of Ce contents (0, 7.63, 14.84, and $21.68 mol\%$) by using the TMA(Thermo-Mechanical Analysis) method. From the measured data, the linear thermal expansion rate, the coefficient of linear thermal expansion and density variation with temperature were calculated, and the best-fitted temperature-dependent equations were recommended. It was shown that the rate and coefficient of $(U_{1-y}Ce_y)O_2$ thermal expansion increased and the density decreased with increasing Ce contents.

U$O_2$핵연료의 기공 특성에 대한 연구 (A Study on the Pore Characteristics of the U$O_2$ Fuel)

  • Song, K-W;K.S. Seo;Sohn, D-S;Kim, S.H.;I.S.Chang;H.S. Chang
    • Nuclear Engineering and Technology
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    • 제23권1호
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    • pp.49-55
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    • 1991
  • AUC공정으로 제조된 $UO_2$분말을 사용하여 소결체를 제조하여 미세 조직과 기공특성에 대하여 시험하였다. 개기공은 소결밀도 증가에 따라서 감소하였으며, 소결밀도 10.45 g/㎤ 이상에서는 거의 소멸하였다. 3$\mu$m보다 작은 크기의 둥근 기공이 모든 밀도에서 나타났고 낮은 밀도에서는 이것외에도 긴 기공이 관찰되었다. 같은 크기의 기공일지라도 밀도가 낮아지면 기공이 더욱 길게 나타났다. 기공크기에 따른 기공 면적의 분포는 mono 모우드이고, 2~3$\mu$m 기공크기에서 최대치를 보이는 분포를 보였다. 또한 밀도가 감소할수록 큰 기공에 관련된 면적이 증가하였다.

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U$O_2$ 핵연료의 노내 기계론적 고밀화 모형 (A Mechanistic Model for In-Reactor Densification of U$O_2$)

  • Woan Hwang;Keum Seok Seo;Ho Chun Suk
    • Nuclear Engineering and Technology
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    • 제17권2호
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    • pp.116-128
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    • 1985
  • 본 논문에는 이산화 우라늄 소결체의 노내고밀화현상을 온도와 미세구조의 함수로 정화하게 예측할 수 있는 기계론적 이론 모형이 개발.기술되어있다. 이 모형은 $UO_2$ 소결체의 결정 입계내에서 공극(vacancy)이 생성 이동되고, 결정입계에서 공극이 소멸되는 현상을 고려하고 있으며, 이 과정에서 일어나는 고밀화의 크기가 핵분열율, 조사시간, $UO_2$ 소결체밀도, 기공 크기의 분포, 결정입크기 및 온도의 함수로 기술되어 있다. 본 모형의 기공 수축에 대한 결과식은 Assmann과 Stehle가 유도한 4개의 온도 영역에 대한 결과식과는 상이한 것으로서, 소결체의 모든 온도 영역에 직접 적용된다. 본 모형에 의한 노내고밀화 크기의 예측치는 실험자료와 아주 잘 일치하며, KEFDA 전산코드에 사용된 경험적 실험 연산식에 비하여 고밀화의 경향과 절대치를 보다 정확히 예측한다.

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A NOVEL APPROACH TO FIND OPTIMIZED NEUTRON ENERGY GROUP STRUCTURE IN MOX THERMAL LATTICES USING SWARM INTELLIGENCE

  • Akbari, M.;Khoshahval, F.;Minuchehr, A.;Zolfaghari, A.
    • Nuclear Engineering and Technology
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    • 제45권7호
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    • pp.951-960
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    • 2013
  • Energy group structure has a significant effect on the results of multigroup transport calculations. It is known that $UO_2-PuO_2$ (MOX) is a recently developed fuel which consumes recycled plutonium. For such fuel which contains various resonant nuclides, the selection of energy group structure is more crucial comparing to the $UO_2$ fuels. In this paper, in order to improve the accuracy of the integral results in MOX thermal lattices calculated by WIMSD-5B code, a swarm intelligence method is employed to optimize the energy group structure of WIMS library. In this process, the NJOY code system is used to generate the 69 group cross sections of WIMS code for the specified energy structure. In addition, the multiplication factor and spectral indices are compared against the results of continuous energy MCNP-4C code for evaluating the energy group structure. Calculations performed in four different types of $H_2O$ moderated $UO_2-PuO_2$ (MOX) lattices show that the optimized energy structure obtains more accurate results in comparison with the WIMS original structure.

핵 연료 요소내의 접촉 열전도도 측정 (Measurement of The Thermal Contact Conductance in Nuclear Fuel Element)

  • ;윤병조
    • Nuclear Engineering and Technology
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    • 제22권1호
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    • pp.75-81
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    • 1990
  • 핵연료봉내의 온도 분포를 결정하는데 있어서 중요한 핵연료소자와 피복판 사이의 접촉 열전도도를 결정하기 위한 실험을 수행하였다. 이 실험에 사용된 측정장치는 접촉압력을 임의로 변화시켜 줄 수 있는 가압기와 열전대, 진공펌프, 핵연료소자, 봉형태의 피복관, 그리고 두 개의 히터 등으로 구성되어 있다. 접촉 열전도도는 $UO_2$ 소자와 Zircaloy-2 피복관 사이의 접촉 압력과 표면 조도를 변화시키면서 측정하였다. 그 결과 두 물체사이의 접촉압력이 증가함에 따라, 그리고 표면이 매끄러울수록 접촉 열전달계수는 증가하였다. 실험에서 얻은 값을 가지고 상관식을 만들었으며 일반적으로 사용되고 있는 상관식과 비교하였다.

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Phase analysis of simulated nuclear fuel debris synthesized using UO2, Zr, and stainless steel and leaching behavior of the fission products and matrix elements

  • Ryutaro Tonna;Takayuki Sasaki;Yuji Kodama;Taishi Kobayashi;Daisuke Akiyama;Akira Kirishima;Nobuaki Sato;Yuta Kumagai;Ryoji Kusaka;Masayuki Watanabe
    • Nuclear Engineering and Technology
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    • 제55권4호
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    • pp.1300-1309
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    • 2023
  • Simulated debris was synthesized using UO2, Zr, and stainless steel and a heat treatment method under inert or oxidizing conditions. The primary U solid phase of the debris synthesized at 1473 K under inert conditions was UO2, whereas a (U, Zr)O2 solid solution formed at 1873 K. Under oxidizing conditions, a mixture of U3O8 and (Fe, Cr)UO4 phases formed at 1473 K, whereas a (U, Zr)O2+x solid solution formed at 1873 K. The leaching behavior of the fission products from the simulated debris was evaluated using two methods: the irradiation method, for which fission products were produced via neutron irradiation, and the doping method, for which trace amounts of non-radioactive elements were doped into the debris. The dissolution behavior of U depended on the properties of the debris and aqueous solution for immersion. Cs, Sr, and Ba leached out regardless of the primary solid phases. The leaching of high-valence Eu and Ru ions was suppressed, possibly owing to their solid-solution reaction with or incorporation into the uranium compounds of the simulated debris.

21 W LED 엔진을 이용한 150 W급 가로등의 최적설계 (150 W LED Streetlight Optimal Design Using 21 W LED Engine)

  • 신왕수;이승민;김범수;박대희
    • 한국전기전자재료학회논문지
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    • 제29권1호
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    • pp.62-67
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    • 2016
  • In this paper, the IES file was measured by applying a secondary optical lens to a 21 W LED engine, and the lighting calculation software RELUX was used to perform simulations with the data file of this measurement. For two-lane (two way) concrete paved roads, six LED engine are applied to each streetlight and simulation results show that Uo (uniformity) 0.56, UI (longitudinal uniformity) 0.86 and TI (threshold iIncrement) 9% which satisfies the required standards. RELUX was also used to LED streetlights by designing them in three dimensions, that is ${\pm}25%$ of the arm length of 2.8 m standardized by the road lighting standards of the Korea Expressway Corporation. Comparative analysis was carried out on adjustments were made in increments of 0.1 m that Uo, UI, and TI values in the range of arm lengths from 2.1 m~3.5 m. For the arm length range of 2.1 m~2.4 m, Uo was high, whereas UI was low. Therefore, we present the optimal light distribution values designed for an arm length of 2.5 m.

희토류금속 분리 및 회수를 위한 분석화학적 연구 (제1보) : 우라늄(VI)의 분리회수를 위한 선택이온교환수지 합성과 우라늄(VI) 금속이온의 흡착특성 (Studies on the New Analytical Methods for Separation and Recovery of Rare Earth Metals (I) : Adsorption Characteristics of U(VI) Ion by New Synthetic Resins with Macrocyclic Compounds)

  • 정오진;정학진;김준태
    • 대한화학회지
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    • 제32권4호
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    • pp.358-370
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    • 1988
  • 클로로메칠화된 스틸렌, 1,4-디비닐벤젠과 동공의 크기를 달리한 여러가지 거대고리화합물을 개시제로 하여 공중합법에 의하여 1%, 2%, 4% 및 10%의 다리결합도를 가진 새로운 이온교환수지를 합성하였다. 그리고 이들 수지에 대한 우라늄(VI), 구리(II), 및 희토류(III) 금속에 대한 흡착특성을 검토하였다. 이 수지들은 강산, 강염기 및 열에 대해서 안정하였으며 pH 4.0이상에서는 $UO_2^{+2}$의 흡착력이 증가하였다. U(Ⅵ)금속이온의 최적흡착시간은 20분이상이였으며 금속이온흡착력은 수지의 다리결합도와 흡착시 사용한 용액의 유전상수크기에 반비례하였다. 그리고 1% 다리결합도수지의 $UO_2^{2+}$이온에 대한 겉보기 용량이 가장 크게 났으며 U(VI)금속이온은 희토류(III)금속이온에 대하여 선택성을 보였다.

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