Densification behaviour of UO2-50%PuO2 pellets by dilatometry

被引:21
|
作者
Kutty, TRG [1 ]
Hegde, PV [1 ]
Keswani, R [1 ]
Khan, KB [1 ]
Majumdar, S [1 ]
Purushotham, DSC [1 ]
机构
[1] Bhabha Atom Res Ctr, Radiomet Div, Trombay 400085, Mumbai, India
关键词
D O I
10.1016/S0022-3115(98)00490-5
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The sintering behaviour of UO2-50%PuO2 pellets has been studied using a dilatometer in inert, reducing and oxidising atmospheres. The shrinkage begins at a much lower temperature in oxidising atmosphere such as CO2 and commercial N-2. The shrinkage rate was found to be maximum for pellets sintered in N-2 atmosphere. The mechanism for the initial stage of sintering was found to be volume diffusion for both oxidising and reducing atmospheres. The activation energy for the initial stages of sintering was found to be 365 and 133 kJ/mol for Ar-8%H-2 and CO2 atmospheres, respectively. The activation energy obtained using the Dorn method matches well with that obtained using the rate controlled sintering process. The lower activation energy obtained in the oxidising atmosphere is explained with the help of models available in the literature. (C) 1999 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:10 / 19
页数:10
相关论文
共 50 条
  • [31] PREPARATION OF IRRADIATION TEST PELLETS OF PUO2-UO2-ZRO2
    CALDWELL, CS
    FISHER, FD
    ROTH, J
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1966, 9 (02): : 544 - +
  • [32] Intrinsic oxygen defects in UO2 (111) and PuO2 (111) surfaces
    Lv, Wenting
    Zhao, Zhongwei
    Sun, Bo
    Guan, Pengfei
    Yang, Yu
    Zhang, Ping
    APPLIED SURFACE SCIENCE, 2023, 610
  • [33] An Evaluation of the Thermophysical Properties of Stoichiometric CeO2 in Comparison to UO2 and PuO2
    Nelson, Andrew T.
    Rittman, Dylan R.
    White, Joshua T.
    Dunwoody, John T.
    Kato, Masato
    McClellan, Kenneth J.
    JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 2014, 97 (11) : 3652 - 3659
  • [34] MELTING HEAT RATING OF UO2-25 WT PERCENT PUO2 FUELS
    LAWRENCE, LA
    CHRISTENSEN, JA
    NUCLEAR TECHNOLOGY, 1971, 12 (04) : 367 - +
  • [35] ENTHALPY OF UO2, THO2, PUO2, AND (U,PU)O2
    FINK, JK
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1981, 39 : 380 - 381
  • [36] IRRADIATION BEHAVIOR OF UO2/PUO2 FUEL IN LIGHT WATER-REACTORS
    GOLL, W
    FUCHS, HP
    MANZEL, R
    SCHLEMMER, FU
    NUCLEAR TECHNOLOGY, 1993, 102 (01) : 29 - 46
  • [37] PROPERTIES OF LENTICULAR PORES IN UO2, (U, PU) O2 AND PUO2
    RONCHI, C
    SARI, C
    JOURNAL OF NUCLEAR MATERIALS, 1974, 50 (01) : 91 - 97
  • [38] POWER TESTS WITH UO2-2 WT PERCENT PUO2 BATCH CORE IN PRTR
    KUTCHER, JW
    HARRIS, RE
    SMITH, RI
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1967, 10 (02): : 517 - &
  • [39] MELTING HEAT RATING OF UO2-25WT PERCENT PUO2 FUELS
    LAWRENCE, LA
    CHRISTEN.JA
    HORN, GR
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1969, 12 (02): : 562 - &
  • [40] POST-EXAMINATION OF UO2-5 WT PERCENT PUO2 FUELS
    ROSS, WJ
    PUECHL, KH
    CALDWELL, CS
    MILES, J
    SHIPKO, F
    JUDD, WC
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1966, 9 (01): : 40 - &