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EFFECT OF $SiO_2-CaO-Cr_2O_3$ ON THE CREEP PROPERTY OF URANIUM DIOXIDE 원문보기

Nuclear engineering and technology : an international journal of the Korean Nuclear Society, v.37 no.3, 2005년, pp.287 - 292  

RHEE YOUNG WOO (Korea Atomic Energy Research Institute) ,  KANG KI WON (Korea Atomic Energy Research Institute) ,  KIM KEON SIK (Korea Atomic Energy Research Institute) ,  YANG JAE HO (Korea Atomic Energy Research Institute) ,  KIM JONG HEON (Korea Atomic Energy Research Institute) ,  SONG KUN WOO (Korea Atomic Energy Research Institute)

Abstract ▼ AI-Helper 아이콘AI-Helper

[ $\pi$ ]The effects of silica-based additives have been investigated to improve the creep property of a $UO_2$ pellet. The additive composition, $50wt\%SiO_2-47wt{\%}CaO-3wt\%Cr_2O_3$ (SCC), was selected according to the dihedral angle and the distribution of the se...

주제어

#Fuel   #Creep  

AI 본문요약
AI-Helper 아이콘 AI-Helper

* AI 자동 식별 결과로 적합하지 않은 문장이 있을 수 있으니, 이용에 유의하시기 바랍니다.

제안 방법

  • creep rate and (2) to evaluate the effects of this novel phase on both the microstructure and the creep rate. The SiO2-CaO-Cr2O3 system was selected from among four candidate systems, SiO2-ZnO, SiO2-CaO-Cr2O3, SiO2- MnO, and SiO2-Y2O3-Cr2O35 by means of a screening test, which covered the distribution of the intergranular glassy phase and the wetting behavior. The creep properties of the SiO2-CaO-Cr2O3-added UO2 pellet were compared with those of pure UO2.
  • The grain sizes of the polished samples were measured using the linear in坨rcept method after being et사led at 1300℃ for 1 h in CO2. The compression creep tests were conducted in a dead load system with a tungsten heating element furnace. The tests were carried out in an Ar-5% H2 atmosphere under 20, 35, 50, and 65 MPa at 1500℃.
  • The purposes of the present investigation are (1) to find a new intergranular phase that can enhance the UO2 creep rate and (2) to evaluate the effects of this novel phase on both the microstructure and the creep rate. The SiO2-CaO-Cr2O3 system was selected from among four candidate systems, SiO2-ZnO, SiO2-CaO-Cr2O3, SiO2- MnO, and SiO2-Y2O3-Cr2O35 by means of a screening test, which covered the distribution of the intergranular glassy phase and the wetting behavior.
  • The samples for the compression creep test were prepared in the same way using 0.07, 0.22, and 0.35 wt% of the 50SiO2-47CaO-3Cr2O3 additive, respectively. The samples were of a cylindrical geometry, ~8 mm in height and ~8 mm in diameter.
  • The compression creep tests were conducted in a dead load system with a tungsten heating element furnace. The tests were carried out in an Ar-5% H2 atmosphere under 20, 35, 50, and 65 MPa at 1500℃. The pure UO2 samples, the reference samples, were also made and tested in the same way.

대상 데이터

  • The additives were determined using two criteria a lower melting point than the sintering temperature and glass forming abilities. The compositions of the additives chosen were 51 SiO2-49ZnO, 50SiO2-47CaO-3Cr2O3, 51SiO2-49MnO, and 42SiO2-53Y2O3-5Cr2O3 in weight percentages from the phase diagrams. Additive powders were ground in ethanol by ball-milling with zirconia balls for 12 h and then dried.

이론/모형

  • The samples were of a cylindrical geometry, ~8 mm in height and ~8 mm in diameter. The sintered density was measured using the water immersion method. All the samples were limited to a density of 95.
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참고문헌 (18)

  1. W.M. Armstrong, A.R. Causey and W.R. Sturrock, 'Creep of Single-Crystal $UO_2$ ,' J. Nucl. Mater., 19,42 (1966) 

    상세보기 crossref

  2. J.L. Routbort and J.C. Voglewede, 'Creep of MixedOxide Fuel Pellets at High Stress,' J. Am. Ceram. Soc., 56,330 (1973) 

    상세보기 crossref

  3. D.B. Knorr, R.M. Cannon and R.L. Coble, 'An Analysis of Diffusion and Duffusional Creep in Stoichiometric and Hyperstoichiometric Uranium Dioxide,' Acta Metal., 37, 2103 (1989) 

    상세보기 crossref

  4. F. Dherbey, F. Louchet, A. Mocellin and S. Leclercq, 'Elevated Temperature Creep of Polycrystalline Uranium Dioxide,' Acta Mater., 50, 1495 (2002) 

    상세보기 crossref

  5. M.S. Seltzer, A.H. Clauer and B.A. Wilcox, 'The influence of stoichiometry on compression creep of uranium dioxide single crystals,' J. Nucl. Mater., 44, 43 (1972) 

    상세보기 crossref

  6. M.S. Seltzer, A.H. Clauer and B.A. Wilcox, 'The Influence of Stoichiometry on Compression Creep of Polycrystalline $UO_{2+x}$ ,' J. Nucl. Mater., 44. 331 (1972) 

    상세보기 crossref

  7. W.M. Armstrong, W.R Irvine and R.H. Martinson, 'Creep Deformation of Stoichiometric Uranium Dioxide,' J. Nucl. Mater., 7, 133 (1962) 

    상세보기 crossref

  8. B. Burton, G.L. Reynolds, J.P. Barnes, 'The Influence of Grain Size on the Creep of Uranium Dioxide,' J. Mater. Sci., 8, 1690 (1973) 

    상세보기 crossref

  9. T.E. Chung and T.J. Davies, 'The Superplastic Creep of Uranium Dioxide,' J. Nucl. Mater., 79,143 (1979) 

    상세보기 crossref

  10. W.M. Armstrong and W.R Irvine, 'Creep of Urania Base Solid Solutions,' J. Nucl. Mater., 12, 261 (1964) 

    상세보기 crossref

  11. Ch. Delafoy, P. Blanpain, S. Lansiart, Ph. Dehaudt, G. Chiarelli and R. Castelli, 'Advanced PWR Fuels for High Burn-up Extension and PCI Constraint Elimination,' Proceedings of IAEA Technical Meeting on Improved Fuel Pellet Materials and Designs., pp. 163-173, October, 2003, Brussels, Belgium 

  12. A.A. Solomon, C.S. Yust and N.H. Packan, 'Primary Creep of $UO_2$ and the Effect of Amorphous Grain Boundary Phases,' J. Nucl. Mater., 110, 333 (1982) 

    상세보기 crossref

  13. K.W. Lay, H.S. Rosembaum, J.H. Davis and M.O. Marlowe, 'Nuclear Fuel,' US Pat. 4869866 (1989) 

  14. K.W. Lay, R.S. Rosembaum and J.H. Davis, 'Nuclear Fuel,' US Pat. 4869867 (1989) 

  15. K.W. Kang, J.H. Yang, K.S. Kim, J.H. Kim and K.W. Song, 'Effect of Additives on Creep Property of $UO_2$ Pellet,' Proceedings of the Kor. Nucl. Soc., Spring Meeting, May 2001 

  16. Y.K. Bibilashvili, F.G. Reshetnikov, V.V. Novikov, A.V. Medvedev, OV. Milovanov, A.Y. Kuleshov, E.N. Mikheev, V.I. Kuznetsov, V.B. Malygin, K.V. Naboichenko, A.N. Sokolov, V.I. Tokarev and Y.V. Pimenov, 'Development of Low-Strain Resistant Fuel for Power Reactor Fuel Rods,' Proceedings of IAEA Technical Meeting on Improved Fuel Pellet Materials and Designs., pp.297-305, October, 2003, Brussels, Belgium 

  17. D.S. Wilkinson, 'Creep Mechanisms in Multiphase Ceramic Materials,' JAm. Ceram. Soc., 81, 275 (1998) 

    상세보기 crossref

  18. Levin, E. M., Robbins, C. R. and McMurdie, R. F., Figs. 101,302,651 and 2388 in Phase Diagrams for Ceramists, ed. by M. K. Reser. American Ceramic Society, Columbus, OH, 1964 

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