Liquidus temperature of irradiated mixed oxide fuels for fast reactors

被引:3
|
作者
Konno, K [1 ]
机构
[1] Tokai Works, Plutonium Fuel Ctr, Japan Nucl Cycle Dev Inst, Tokai, Ibaraki 3191194, Japan
关键词
liquidus; solidus; mixed-oxide fuel; fast reactors; melting point; burnup; burnup dependence; oxygen-to-metal ratio; plutonium fraction; americium fraction; ideal solution model; safety;
D O I
10.3327/jnst.39.1299
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
引用
收藏
页码:1299 / 1302
页数:4
相关论文
共 50 条
  • [21] STUDIES IN MIXED-OXIDE IRRADIATED FUELS - TRANSPORT OF CLADDING COMPONENTS
    JOHNSON, C
    CROUTHAM.C
    CHEN, H
    BLACKBUR.P
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1969, 12 (02): : 565 - &
  • [22] SHIPPING IRRADIATED FUELS FROM NUCLEAR REACTORS
    BROWN, SH
    JOM-JOURNAL OF METALS, 1964, 16 (01): : 130 - &
  • [23] A review of microstructural features in fast reactor mixed oxide fuels
    Parrish, Riley
    Aitkaliyeva, Assel
    JOURNAL OF NUCLEAR MATERIALS, 2018, 510 : 644 - 660
  • [24] EVALUATION OF RADIAL TEMPERATURE DISTRIBUTION IN MIXED OXIDE FUELS
    Roman, Mihaela-Roxana
    Ionescu, Victor Dragos
    Olteanu, Gheorghe
    Prisecaru, Ilie
    2019 INTERNATIONAL CONFERENCE ON ENERGY AND ENVIRONMENT (CIEM), 2019, : 109 - 112
  • [25] UTILIZATION OF CARBIDE FUELS IN FAST REACTORS
    SHAPIRO, MM
    STRASSER, AA
    CHERRY, BH
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1968, 11 (02): : 518 - &
  • [26] PLUTONIUM CERAMIC FUELS FOR FAST REACTORS
    MURRAY, P
    BOLTAX, A
    BIANCHER.AM
    RAY, WE
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1968, 11 (02): : 518 - &
  • [27] Analysis of fabrication and crack-induced porosity migration in mixed oxide fuels for sodium fast reactors by the finite element method
    Barani, Tommaso
    Ramiere, Isabelle
    Michel, Bruno
    JOURNAL OF NUCLEAR MATERIALS, 2022, 558
  • [28] THERMODYNAMIC ANALYSIS OF MIXED CARBIDE, CARBONITRIDE AND NITRIDE FUELS FOR FAST BREEDER-REACTORS
    SRIVASTAVA, D
    GARG, SP
    GOSWAMI, GL
    JOURNAL OF NUCLEAR MATERIALS, 1989, 161 (01) : 44 - 56
  • [29] DISTRIBUTION OF GASEOUS FISSION-PRODUCTS IN IRRADIATED MIXED-OXIDE FUELS
    JOHNSON, CE
    STEIDL, DV
    CROUTHAMEL, CE
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1971, 14 (NAPR): : 27 - +
  • [30] Dissolution behavior of irradiated mixed-oxide fuels with different plutonium contents
    Ikeuchi, Hirotomo
    Shibata, Atsuhiro
    Sano, Yuichi
    Koizumi, Tsutomu
    ATALANTE 2012 INTERNATIONAL CONFERENCE ON NUCLEAR CHEMISTRY FOR SUSTAINABLE FUEL CYCLES, 2012, 7 : 77 - 83