Influence of low temperature air oxidation on the dissolution behaviour of UO2 and MOX spent fuel

被引：0
|
作者：
Departamento de Fision Nuclear, Madrid, Spain [1 ]
机构：
来源：
J Alloys Compd | / 573-576期
关键词：
D O I：
暂无
中图分类号：
学科分类号：
摘要：
引用
收藏
相关论文
共 50 条
  • [21] THE INFLUENCE OF MOISTURE ON AIR OXIDATION OF UO2 - CALCULATIONS AND OBSERVATIONS
    TAYLOR, P
    LEMIRE, RJ
    WOOD, DD
    NUCLEAR TECHNOLOGY, 1993, 104 (02) : 164 - 170
  • [22] FUEL PERFORMANCE CODE COSMOS FOR ANALYSIS OF LWR UO2 AND MOX FUEL
    Lee, Byung-Ho
    Koo, Yang-Hyun
    Oh, Jae-Yong
    Cheon, Jin-Sik
    Tahk, Young-Wook
    Sohn, Dong-Seong
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2011, 43 (06) : 499 - 508
  • [23] Uraninite and UO2 in spent nuclear fuel: A comparison
    Janeczek, J
    Ewing, RC
    Oversby, VM
    Werme, LO
    JOURNAL OF NUCLEAR MATERIALS, 1996, 238 (01) : 121 - 130
  • [24] THE CORROSION OF SPENT UO2 FUEL IN SYNTHETIC GROUNDWATER
    FORSYTH, RS
    WERME, LO
    BRUNO, J
    JOURNAL OF NUCLEAR MATERIALS, 1986, 138 (01) : 1 - 15
  • [25] α-radiolysis and α-radiation damage effects on UO2 dissolution under spent fuel storage conditions
    Rondinella, VV
    Matzke, H
    Cobos, J
    Wiss, T
    SCIENTIFIC BASIS FOR NUCLEAR WASTE MANAGEMENT XXII, 1999, 556 : 447 - 454
  • [26] Water corrosion of spent nuclear fuel: radiolysis driven dissolution at the UO2/water interface
    Springell, Ross
    Rennie, Sophie
    Costelle, Leila
    Darnbrough, James
    Stitt, Camilla
    Cocklin, Elizabeth
    Lucas, Chris
    Burrows, Robert
    Sims, Howard
    Wermeille, Didier
    Rawle, Jonathan
    Nicklin, Chris
    Nuttall, William
    Scott, Thomas
    Lander, Gerard
    FARADAY DISCUSSIONS, 2015, 180 : 301 - 311
  • [27] DISSOLUTION OF IRRADIATED UO2 FUEL IN GROUNDWATER.
    Johnson, L.H.
    Atomic Energy of Canada Limited, AECL (Report), 1982,
  • [28] A Comparative Study on the Safety and Kinetic Parameters of UO2 and MOX Fuel
    Hassan, Mohga
    ARAB JOURNAL OF NUCLEAR SCIENCES AND APPLICATIONS, 2016, 49 (01): : 53 - 60
  • [29] SGMP - AN ADVANCED METHOD FOR FABRICATION OF UO2 AND MOX FUEL PELLETS
    ZIMMER, E
    GANGULY, C
    BORCHARDT, J
    LANGEN, H
    JOURNAL OF NUCLEAR MATERIALS, 1988, 152 (2-3) : 169 - 177
  • [30] A mechanistic fission gas behaviour model for UO2 and MOX fuels
    Noirot, L
    Garcia, P
    Struzik, C
    FISSION GAS BEHAVIOUR IN WATER REACTOR FUELS, SEMINAR PROCEEDINGS, 2002, : 131 - 149
12345