Radionuclide release for unsaturated spent fuel tests - First 1.6 years

被引:0
|
作者
Finn, PA
Wolf, SF
Bates, JK
机构
关键词
D O I
暂无
中图分类号
TE [石油、天然气工业]; TK [能源与动力工程];
学科分类号
0807 ; 0820 ;
摘要
引用
收藏
页码:390 / 392
页数:3
相关论文
共 50 条
  • [1] Radionuclide release from spent MOX fuel
    Loida, A
    Grambow, B
    Karsten, G
    Dressler, P
    [J]. SCIENTIFIC BASIS FOR NUCLEAR WASTE MANAGEMENT XXI, 1998, 506 : 923 - 924
  • [2] Radionuclide release from research reactor spent fuel
    Curtius, H.
    Kaiser, G.
    Mueller, E.
    Bosbach, D.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2011, 416 (1-2) : 211 - 215
  • [3] Can spent nuclear fuel decay heat prevent radionuclide release?
    Jerden, JL
    Goldberg, MM
    Cunnane, JC
    Bauer, TH
    Wigeland, RA
    Nietert, RE
    [J]. SCIENTIFIC BASIS FOR NUCLEAR WASTE MANAGEMENT XXVIII, 2004, 824 : 101 - 106
  • [4] The release of cesium and the actinides from spent fuel under unsaturated conditions
    Finn, PA
    Hoh, JC
    Wolf, SF
    Slater, SA
    Bates, JK
    [J]. SCIENTIFIC BASIS FOR NUCLEAR WASTE MANAGEMENT XIX, 1996, 412 : 75 - 81
  • [5] Diffusion in a Variable Aperture Slot: Impact on Radionuclide Release from a Repository for Spent Fuel
    Winberg-Wang, Helen
    [J]. NUCLEAR TECHNOLOGY, 2018, 204 (02) : 184 - 194
  • [6] Spent fuel radionuclide source-term model for assessing spent fuel performance in geological disposal. Part I: Assessment of the instant release fraction
    Johnson, L
    Ferry, C
    Poinssot, C
    Lovera, P
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2005, 346 (01) : 56 - 65
  • [7] Congruent and incongruent radionuclide release during matrix dissolution of partly oxidized high burnup spent fuel
    Loida, A
    Grambow, B
    Geckeis, H
    [J]. SCIENTIFIC BASIS FOR NUCLEAR WASTE MANAGEMENT XXIV, 2000, 663 : 417 - 426
  • [8] The release of uranium, plutonium, cesium, strontium, technetium and iodine from spent fuel under unsaturated conditions
    Finn, PA
    Hoh, JC
    Wolf, SF
    Slater, SA
    Bates, JK
    [J]. RADIOCHIMICA ACTA, 1996, 74 : 65 - 71
  • [9] Radionuclide release from high burnup spent fuel during corrosion in salt brine in the presence of hydrogen overpressure
    Loida, A
    Metz, V
    Kienzler, B
    Geckeis, H
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2005, 346 (01) : 24 - 31
  • [10] Modeling radionuclide release of TRISO bearing fuel compacts during post-irradiation annealing tests
    Schappel, D.
    Terrani, K.
    Snead, L. L.
    Wirth, B. D.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2020, 357