Cermet fuel for fast reactor - Fabrication and characterization

被引：7
|
作者：
Mishra, Sudhir [1 ]
Kutty, P. S. [1 ]
Kutty, T. R. G. [1 ]
Das, Shantanu [2 ]
Dey, G. K. [3 ]
Kumar, Arun [1 ]
机构：
[1] Bhabha Atom Res Ctr, Radiomet Div, Bombay 400085, Maharashtra, India
[2] Bhabha Atom Res Ctr, Uranium Extract Div, Bombay 400085, Maharashtra, India
[3] Bhabha Atom Res Ctr, Div Mat Sci, Bombay 400085, Maharashtra, India
来源：
JOURNAL OF NUCLEAR MATERIALS | 2013年 / 442卷 / 1-3期
关键词：
US PERSPECTIVE; INERT MATRIX; EBR-II; EXPERIENCE; ALLOYS;
D O I：
10.1016/j.jnucmat.2013.08.051
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
(U, Pu)O-2 ceramic fuel is the well-established fuel for the fast reactors and (U, Pu, Zr) metallic fuel is the future fuel. Both the fuels have their own merits and demerits. Optimal solution may lie in opting for a fuel which combines the favorable features of both fuel systems. The choice may be the use of cermet fuel which can be either (U, PuO2) or (Enriched U, UO2). In the present study, attempt has been made to fabricate (Natural U, UO2) cermet fuel by powder metallurgy route. Characterization of the fuel has been carried out using dilatometer, differential thermal analyzer, X-ray diffractometer, and Scanning Electron Microscope. The results show a high solidus temperature, high thermal expansion, presence of porosities, etc. in the fuel. The thermal conductivity of the fuel has also been measured. X-ray diffraction study on the fuel compact reveals presence of alpha U and UO2 phases in the matrix of the fuel. (C) 2013 Elsevier B.V. All rights reserved.
引用
收藏
页码：400 / 407
页数：8
相关论文
共 50 条
  • [1] Cermet fuel for fast reactor - Fabrication and characterization (vol 442, pg 400, 2013)
    Mishra, Sudhir
    Kutty, P. S.
    Kutty, T. R. G.
    Das, Shantanu
    Dey, G. K.
    Kumar, Arun
    JOURNAL OF NUCLEAR MATERIALS, 2018, 512 : 480 - 480
  • [2] STATUS OF FAST-REACTOR FUEL FABRICATION
    PUECHL, KH
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1966, 9 (02): : 545 - +
  • [3] FAST-REACTOR FUEL FABRICATION DEVELOPMENT
    PARKINSON, N
    NELSON, RL
    KENT, WCL
    NUCLEAR ENERGY-JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1981, 20 (01): : 55 - 61
  • [4] FAST REACTOR FUEL FABRICATION DEVELOPMENT.
    Parkinson, N.
    Nelson, R.L.
    Kent, W.C.L.
    Nuclear Energy, 1981, 20 (01): : 55 - 61
  • [5] Gas-cooled fast reactor fuel fabrication
    Fielding, Randall
    Meyer, Mitch
    Jue, Jan-Fong
    Gan, Jian
    JOURNAL OF NUCLEAR MATERIALS, 2007, 371 (1-3) : 243 - 249
  • [6] SAFEGUARDED FAST-REACTOR FUEL FABRICATION PROCESSES
    SPINRAD, BI
    GREENE, KL
    AZARFAR, MA
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1981, 39 : 222 - 223
  • [7] FAST-REACTOR FUEL FABRICATION, REPROCESSING AND TRANSPORT
    ALLARDICE, RH
    HARRIS, DW
    KENT, WCL
    THORNTON, DEJ
    WARD, MD
    NUCLEAR ENERGY-JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1986, 25 (02): : 93 - 100
  • [8] FRENCH FAST BREEDER REACTOR-FUEL FABRICATION
    BAILLY, H
    VIALARD, JL
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 32 (JUN): : 228 - 230
  • [9] FAST REACTOR FUEL FABRICATION, REPROCESSING AND TRANSPORT.
    Allardice, R.H.
    Harris, D.W.
    Kent, W.C.L.
    Thornton, D.E.J.
    Ward, M.D.
    Nuclear Energy, 1986, 25 (02): : 93 - 100
  • [10] SECURING THE REMOTE FABRICATION OF FAST-REACTOR FUEL
    不详
    NUCLEAR ENGINEERING INTERNATIONAL, 1984, 29 (351): : 21 - 23
12345