Helium in inert matrix dispersion fuels

被引:18
作者
van Veen, A
Konings, RJM
Fedorov, AV
机构
[1] Delft Univ Technol, Interfac Reactor Inst, NL-2629 JB Delft, Netherlands
[2] Commiss European Communities, Joint Res Ctr, Inst Transuranium Elements, D-76125 Karlsruhe, Germany
关键词
D O I
10.1016/S0022-3115(03)00173-9
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The behaviour of helium, an important decay product in the transmutation chains of actinides, in dispersion-type inert matrix fuels is discussed. A phenomenological description of its accumulation and release in CERCER and CERMET fuel is given. A summary of recent He-implantation studies with inert matrix metal oxides (ZrO2, MgAl2O4, MgO and Al2O3) is presented. A general picture is that for high helium concentrations helium and vacancy defects form helium clusters which convert into over-pressurized bubbles. At elevated temperature helium is released from the bubbles. On some occasions thermal stable nano-cavities or nano-pores remain. On the basis of these results the consequences for helium induced swelling and helium storage in oxide matrices kept at 800-1000 degreesC will be discussed. In addition, results of He-implantation studies for metal matrices (W, Mo, Nb and V alloys) will be presented. Introduction of helium in metals at elevated temperatures leads to clustering of helium to bubbles. When operational temperatures are higher than 0.5 melting temperature, swelling and helium embrittlement might occur. (C) 2003 Published by Elsevier Science B.V.
引用
收藏
页码:77 / 84
页数:8
相关论文
共 50 条
  • [31] Categorisation and priorities for future research on inert matrix fuels: An extended synthesis of the panel discussions
    Chawla, R
    Konings, RJM
    PROGRESS IN NUCLEAR ENERGY, 2001, 38 (3-4) : 455 - 458
  • [32] Dispersion type zirconium matrix fuels fabricated by capillary impregnation method
    Savchenko, A.
    Konovalov, I.
    Vatulin, A.
    Morozov, A.
    Orlov, V.
    Uferov, O.
    Ershov, S.
    Laushkin, A.
    Kulakov, G.
    Maranchak, S.
    Petrova, Z.
    JOURNAL OF NUCLEAR MATERIALS, 2007, 362 (2-3) : 356 - 363
  • [33] Elements of comparison between different inert matrix fuels as regards plutonium utilisation and safety coefficients
    Baldi, S
    Porta, J
    PROGRESS IN NUCLEAR ENERGY, 2001, 38 (3-4) : 375 - 378
  • [34] Preliminary fabrication and characterization of inert matrix and thoria fuels for plutonium disposition in light water reactors
    Vettraino, F.
    Magnani, G.
    La Torretta, T.
    Marmo, E.
    Coelli, S.
    Luzzi, L.
    Ossi, P.
    Zappa, G.
    Journal of Nuclear Materials, 1999, 274 (01): : 23 - 33
  • [35] Burnup simulations and spent fuel characteristics of ZrO2 based inert matrix fuels
    Schneider, E. A.
    Deinert, M. R.
    Herring, S. T.
    Cady, K. B.
    JOURNAL OF NUCLEAR MATERIALS, 2007, 361 (01) : 41 - 51
  • [36] Preliminary fabrication and characterisation of inert matrix and thoria fuels for plutonium disposition in light water reactors
    Vettraino, F
    Magnani, G
    La Torretta, T
    Marmo, E
    Coelli, S
    Luzzi, L
    Ossi, P
    Zappa, G
    JOURNAL OF NUCLEAR MATERIALS, 1999, 274 (1-2) : 23 - 33
  • [37] Radiotoxicity hazard of inert matrix fuels after burning minor actinides in light water reactors
    Shelley, A
    Akie, H
    Takano, H
    Sekimoto, H
    PROGRESS IN NUCLEAR ENERGY, 2001, 38 (3-4) : 439 - 442
  • [38] Fabrication and characterization of silicon nitride-based inert matrix fuels sintered with magnesium silicates
    Usuki, Toshiyuki
    Yoshida, Katsumi
    Yano, Toyohiko
    Miwa, Shuhei
    Osaka, Masahiko
    PROGRESS IN NUCLEAR ENERGY, 2011, 53 (07) : 1078 - 1081
  • [39] The fabrication and irradiation of plutonium-containing inert matrix fuels for the 'Once Though Then Out' experiment
    Schram, RPC
    van der Laan, RR
    Klaassen, FC
    Bakker, K
    Yamashita, T
    Ingold, F
    JOURNAL OF NUCLEAR MATERIALS, 2003, 319 : 118 - 125
  • [40] DISPERSION OF HELIUM
    MANSFIELD, CR
    PECK, ER
    JOURNAL OF THE OPTICAL SOCIETY OF AMERICA, 1969, 59 (02) : 199 - +