• Title/Summary/Keyword: UO2

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Effect of ${Gd_2}{O_3}$ Addition on the Sintered Density and Resintered Density in <${UO_2}-{Gd_2}{O_3}$ Pellets (${UO_2}-{Gd_2}{O_3}$소결체에서 ${Gd_2}{O_3}$첨가가 소결 및 재소결밀도에 미치는 영향)

  • Baek, Jong-Hyeok
    • Korean Journal of Materials Research
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    • v.5 no.3
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    • pp.364-370
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    • 1995

  • ex-AUC U$O_{2}$ 분말과 $Gd_{2}$O_{3}$ 분말을 기계적으로 혼합하여 소결한 U$O_{2}$-$Gd_{2}$O_{3}$ 소결체의 밀도 변화와 재소결 후 밀도변화를 기공크기 및 분포의 변화로 서술하였다. 수소분위기에서 175$0^{\circ}C$, 4시간 동안 소결하였을 때, 순수 U$O_{2}$의 소결밀도는 97.2% T.D.였으나 6wt% $Gd_{2}$O_{3}$ 첨가까지는 U$O_{2}$-$Gd_{2}$O_{3}$의 소결밀도는 $U^{+4}$와 $Gd^{+4}$의 상호확산 때문에 약 90% T.D.로 급격히 감소하였다. 그러나 6wt% 이상의 $Gd_{2}$O_{3}$가 첨가되면 우라늄이온 산화아와 산소침입으로 인하여 소결밀도는 오히려 증가하였다. 1$700^{\circ}C$에서 재소결시킬 때 순수 U$O_{2}$ 소결체에서는 재소결 시간에 따라 밀도증가가 발생하였다. U$O_{2}$-$Gd_{2}$O_{3}$ 소결체 경우에는 재소결시 밀도가 감소하였으나 재소결 시간이 증가함에 따라 다시 밀도는 증가하였고, 6wt%$Gd_{2}$O_{3}$가 첨가된 U$O_{2}$-$Gd_{2}$O_{3}$ 소결체에서 밀도가 가장 많이 감소하였다.

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Simulation of reactivity-initiated accident transients on UO2-M5® fuel rods with ALCYONE V1.4 fuel performance code

  • Guenot-Delahaie, Isabelle;Sercombe, Jerome;Helfer, Thomas;Goldbronn, Patrick;Federici, Eric;Jolu, Thomas Le;Parrot, Aurore;Delafoy, Christine;Bernaudat, Christian
    • Nuclear Engineering and Technology
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    • v.50 no.2
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    • pp.268-279
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    • 2018

  • The ALCYONE multidimensional fuel performance code codeveloped by the CEA, EDF, and AREVA NP within the PLEIADES software environment models the behavior of fuel rods during irradiation in commercial pressurized water reactors (PWRs), power ramps in experimental reactors, or accidental conditions such as loss of coolant accidents or reactivity-initiated accidents (RIAs). As regards the latter case of transient in particular, ALCYONE is intended to predictively simulate the response of a fuel rod by taking account of mechanisms in a way that models the physics as closely as possible, encompassing all possible stages of the transient as well as various fuel/cladding material types and irradiation conditions of interest. On the way to complying with these objectives, ALCYONE development and validation shall include tests on $PWR-UO_2$ fuel rods with advanced claddings such as M5(R) under "low pressure-low temperature" or "high pressure-high temperature" water coolant conditions. This article first presents ALCYONE V1.4 RIA-related features and modeling. It especially focuses on recent developments dedicated on the one hand to nonsteady water heat and mass transport and on the other hand to the modeling of grain boundary cracking-induced fission gas release and swelling. This article then compares some simulations of RIA transients performed on $UO_2$-M5(R) fuel rods in flowing sodium or stagnant water coolant conditions to the relevant experimental results gained from tests performed in either the French CABRI or the Japanese NSRR nuclear transient reactor facilities. It shows in particular to what extent ALCYONE-starting from base irradiation conditions it itself computes-is currently able to handle both the first stage of the transient, namely the pellet-cladding mechanical interaction phase, and the second stage of the transient, should a boiling crisis occur. Areas of improvement are finally discussed with a view to simulating and analyzing further tests to be performed under prototypical PWR conditions within the CABRI International Program. M5(R) is a trademark or a registered trademark of AREVA NP in the USA or other countries.

  • https://doi.org/10.1016/j.net.2017.12.006 인용 PDF KSCI

Feasibility Study of a Device for Decladding and Dry Pulverizing/Mixing Spent Fuel (사용후핵연료의 탈피복 및 건식 분말화/혼합 장치의 타당성 분석)

  • 정재후;윤지섭;홍동회;김영환;박기용;진재현
    • Proceedings of the Korean Society of Precision Engineering Conference
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    • 2002.05a
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    • pp.840-843
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    • 2002

  • The dry pulverizing/Mixing device is used to deal with the spent fuels for the safe disposal. The separated pellets from hulls by a slitting device are put and oxidized from UO$_2$ solid pellet to U$_3$O$\_$8/ powder in the device. The device have been developed based on a voloxidation method which is one of several dry de-cladding methods. We have benchmarked dry de-cladding methods, analyzed applicability to the advanced spent fuel management process, integrated and compared several configuration, and finally derived detailed specifications proper to requirements for the device. Also, thermal characteristics of the device such as thermal stress and strain have been analyzed by the commercial software, 1-DEAS, and the reliability of the results have been verified by the KOLAS(Korea Laboratory Accreditation Scheme). The UO$_2$ solid pellets are put in the device which has a capacity of 20 kgHM per a batch, heated up about 600$^{\circ}C$ in the air environment. Then, the UO$_2$ solid pellets are oxidized into the U$_3$O$\_$8/ powder, and the powder is collected in a special vessel. The device has been designed and developed as fellows: the multi-staged fine hole meshes are used to reduce the size of the powder gradually, heat and air(oxygen) are supplied continuously to reduce the reaction time, and slight vibration effect are applied to collect powder cling to the device.

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