A science-based mixed oxide property model for developing advanced oxide nuclear fuels

被引:2
|
作者
Kato, Masato [1 ,2 ,3 ,4 ]
Oki, Takumi [2 ]
Watanabe, Masashi [1 ,2 ,3 ,4 ]
Hirooka, Shun [2 ,3 ]
Vauchy, Romain [2 ]
Ozawa, Takayuki [2 ,3 ]
Uwaba, Tomoyuki [4 ]
Ikusawa, Yoshihisa [2 ]
Nakamura, Hiroki [5 ]
Machida, Masahiko [5 ]
机构
[1] Japan Atom Energy Agcy, Nucl Plant Innovat Promot Off, Oarai, Ibaraki 3111393, Japan
[2] Japan Atom Energy Agcy, Fuel Engn Dept, Plutonium Fuel Dev Ctr, Tokai, Japan
[3] Japan Atom Energy Agcy, Fuel Cycle Design Off, Oarai, Japan
[4] Japan Atom Energy Agcy, Fuels & Mat Dept, Oarai Res & Dev Ctr, Oarai, Japan
[5] Japan Atom Energy Agcy, Ctr Computat Sci & Esyst, Kashiwa, Japan
关键词
Bredig transition; electronic conduction; MOX fuel; phonon conduction; physical property; plutonium; ELECTRICAL-CONDUCTIVITY; THERMAL-CONDUCTIVITY; THERMOPHYSICAL PROPERTIES; HIGH-TEMPERATURES; (U; PU; PLUTONIA; URANIA; UO2;
D O I
10.1111/jace.19609
中图分类号
TQ174 [陶瓷工业]; TB3 [工程材料学];
学科分类号
0805 ; 080502 ;
摘要
Herein, a science-based uranium and plutonium mixed oxide (MOX) property model is derived for determining the properties of MOX fuel and analyzing their performance as functions of Pu content, minor-actinide content, oxygen-to-metal ratio, and temperature. The property model is constructed by evaluating the effect of phonons and electronic defects on the heat capacity and thermal conductivity of MOX fuels. The effect of phonons was evaluated based on experimental datasets related to lattice parameters, thermal expansion, and sound speeds. Moreover, the effect of electronic defects was determined by analyzing oxygen-potential data based on defect chemistry. Furthermore, the model evaluated the effect of the Bredig transition on the thermal properties of MOX fuel by analyzing the irradiation test results. The derived property model is applied to the performance code to analyze fast reactor fuel pins.
引用
收藏
页码:2998 / 3011
页数:14
相关论文
共 50 条
  • [31] New Approaches to Processing and Fabrication of Oxide Nuclear Fuels
    Kulyako, Yu. M.
    Trofimov, T. I.
    Il'in, E. G.
    Myasoedov, B. F.
    RUSSIAN JOURNAL OF GENERAL CHEMISTRY, 2011, 81 (09) : 1960 - 1965
  • [32] A MODEL SCIENCE-BASED LEARNING STEM PROGRAM
    Cieslinski, Benjamin
    Gharib, Mohamed
    Creel, Brady
    Katbeh, Tala
    PROCEEDINGS OF THE ASME INTERNATIONAL MECHANICAL ENGINEERING CONGRESS AND EXPOSITION, 2019, VOL 5, 2019,
  • [33] Educating the physical security professional: developing a science-based curriculum
    Michael Patrick Coole
    David Jonathan Brooks
    Anthony Minnaar
    Security Journal, 2018, 31 : 524 - 547
  • [34] INVITRO DISSOLUTION OF RESPIRABLE AEROSOLS OF INDUSTRIAL URANIUM AND PLUTONIUM MIXED-OXIDE NUCLEAR-FUELS
    EIDSON, AF
    MEWHINNEY, JA
    HEALTH PHYSICS, 1983, 45 (06): : 1023 - 1037
  • [35] Educating the physical security professional: developing a science-based curriculum
    Coole, Michael Patrick
    Brooks, David Jonathan
    Minnaar, Anthony
    SECURITY JOURNAL, 2018, 31 (02) : 524 - 547
  • [36] Recent development of mixed transition metal oxide and graphene/mixed transition metal oxide based hybrid nanostructures for advanced supercapacitors
    Low, Wei Hau
    Khiew, Poi Sim
    Lim, Siew Shee
    Siong, Chiu Wee
    Ezeigwe, Ejikeme Raphael
    JOURNAL OF ALLOYS AND COMPOUNDS, 2019, 775 : 1324 - 1356
  • [37] Recent development of mixed transition metal oxide and graphene/mixed transition metal oxide based hybrid nanostructures for advanced supercapacitors
    Low, Wei Hau
    Khiew, Poi Sim
    Lim, Siew Shee
    Siong, Chiu Wee
    Ezeigwe, Ejikeme Raphael
    Journal of Alloys and Compounds, 2020, 775 : 1324 - 1356
  • [38] FINAL-STAGE DENSIFICATION OF MIXED-OXIDE FUELS
    ROUTBORT, JL
    VOGLEWEDE, JC
    WILKINSON, DS
    JOURNAL OF NUCLEAR MATERIALS, 1979, 80 (02) : 348 - 355
  • [39] Liquidus temperature of irradiated mixed oxide fuels for fast reactors
    Konno, K
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2002, 39 (12) : 1299 - 1302
  • [40] THERMODYNAMIC BEHAVIOR OF (U, PU) MIXED-OXIDE FUELS
    JAVED, NA
    JOURNAL OF NUCLEAR MATERIALS, 1973, 47 (03) : 336 - 344