Cermet sphere-pac concept for inert matrix fuel

被引:22
|
作者
Pouchon, MA [1 ]
Nakamura, M
Hellwig, C
Ingold, F
Degueldre, C
机构
[1] Paul Scherrer Inst, Lab Mat Behaviour, Dept Nuclear Energy & Safety, LVW, CH-5232 Villigen, Switzerland
[2] Japan Nucl Mat Behav, Ibaraki 3191194, Japan
关键词
D O I
10.1016/S0022-3115(03)00131-4
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
In the inert matrix fuel concept, plutonium reprocessed from spent fuel is burned in an inert matrix, e.g. yttria-stabilized zirconia. Coming from wet reprocessing, the internal gelation can perform an easy micro-spheres production. Utilization of these particles in a sphere-pac realizes a direct fuel production. Besides being economical, this direct usage offers an almost dustless fabrication. One disadvantage of yttria-stabilized zirconia as matrix is its low thermal conductivity. A further reduction by the macroscopic structure of a sphere bed seems unacceptable. This can be eluded by the insertion of a highly conducting phase. Similar to the cermet concept with the embedment of ceramic fuel into metal, the infiltration of a fine metal fraction into a coarse ceramic fuel fraction is studied here. The initial thermal conductivity shows much higher calculated values and the sintering behaviour is also clearly enhanced compared to the pure ceramic bed. (C) 2003 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:37 / 43
页数:7
相关论文
共 50 条
  • [21] MODELING FUEL SWELLING AND GAS-RELEASE IN SPHERE-PAC CARBIDE FUELS
    ADES, M
    PEDDICORD, KL
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 32 (JUN): : 279 - 280
  • [22] CONTROL AND INSPECTION SYSTEMS FOR SPHERE-PAC LOADING
    ANGELINI, P
    ALLEN, EJ
    AMERICAN CERAMIC SOCIETY BULLETIN, 1979, 58 (03): : 392 - 392
  • [23] The MARINE experiment: Irradiation of sphere-pac fuel and pellets of UO2-x for americium breading blanket concept
    D'Agata, E.
    Hania, P. R.
    Freis, D.
    Somers, J.
    Bejaoui, S.
    Charpin, F. F.
    Baas, P. J.
    Okel, R. A. F.
    van Til, S.
    Lapetite, J. -M.
    Delage, F.
    NUCLEAR ENGINEERING AND DESIGN, 2017, 311 : 131 - 141
  • [24] RECENT DEVELOPMENT OF SPHERE-PAC LOADING PROCESS
    SUCHOMEL, RR
    LACKEY, WJ
    JOURNAL OF THE ELECTROCHEMICAL SOCIETY, 1978, 125 (08) : C361 - C361
  • [25] MEASUREMENT OF THE INTERNAL-FRICTION ANGLE FOR UO2 SPHERE-PAC FUEL
    JENKS, RP
    PEDDICORD, KL
    KENNEDY, TC
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1983, 44 : 255 - 256
  • [26] SPACON - A theoretical model for calculating the heat transport properties in sphere-pac fuel pins
    Botta, F
    Hellwig, C
    NUCLEAR SCIENCE AND ENGINEERING, 2000, 135 (02) : 165 - 176
  • [27] THERMAL PERFORMANCE MODELING OF SPHERE-PAC MIXED CARBIDE FAST-REACTOR FUEL
    ADES, MJ
    PEDDICORD, KL
    MONTGOMERY, SD
    NUCLEAR SCIENCE AND ENGINEERING, 1983, 84 (01) : 47 - 58
  • [28] IN-REACTOR THERMAL-CONDUCTIVITY OF UO2 SPHERE-PAC FUEL
    CUNNINGHAM, ME
    BARNER, JO
    FRESHLEY, MD
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1981, 38 (JUN): : 276 - 277
  • [29] THERMAL-CONDUCTIVITY DURING INITIAL-STAGE RESTRUCTURING IN SPHERE-PAC FUEL
    ADES, M
    PEDDICORD, KL
    GUENTHER, RJ
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1978, 30 (NOV): : 531 - 532
  • [30] THERMAL PERFORMANCE AND RESTRUCTURING OF PELLET AND SPHERE-PAC FUELS
    FITTS, RB
    DECARLO, VA
    LONG, EL
    OLSEN, AR
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1970, 13 (02): : 549 - &