Fission products stability in uranium dioxide

被引:48
|
作者
Brillant, G. [1 ]
Gupta, F. [2 ]
Pasturel, A. [3 ,4 ]
机构
[1] LETR & LIMSI, SEMIC, DPAM, Inst Radioprotect & Surete Nucl, F-13115 St Paul Les Durance, France
[2] BARE, SEGRE, DSR, Inst Radioprotect & Surete Nucl, F-92262 Fontenay Aux Roses, France
[3] UJF, CNRS, INP Grenoble, F-38402 St Martin Dheres, France
[4] CNRS, Lab Phys & Modelisat Milieux Condenses, F-38042 Grenoble 09, France
关键词
X-RAY-DIFFRACTION; AB-INITIO; STRUCTURAL STABILITY; RUTHENIUM RELEASE; NUCLEAR-FUELS; POINT-DEFECTS; OXIDE FUELS; HIGH-BURNUP; PART I; UO2;
D O I
10.1016/j.jnucmat.2011.02.054
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Fission product stability in nuclear fuels is investigated using density functional theory (DFT). In particular, incorporation and solution energies of He, Kr, Xe, I, Te, Ru, Sr and Ce in pre-existing trap sites of UO2 (vacancies, interstitials, U-O divacancy, and Schottky trio defects) are calculated using the projector-augmented-wave method as implemented in the Vienna ab initio simulation package. Correlation effects are taken into account within the DFT+U approach. The stability of many binary and ternary compounds in comparison to soluted atoms is also explored. Finally the involvement of FP in the formation of metallic and oxide precipitates in oxide fuels is discussed in the light of experimental results. (C) 2011 Elsevier B.V. All rights reserved.
引用
收藏
页码:170 / 176
页数:7
相关论文
共 50 条
  • [1] THE STABILITY OF FISSION-PRODUCTS IN URANIUM-DIOXIDE
    GRIMES, RW
    CATLOW, CRA
    PHILOSOPHICAL TRANSACTIONS OF THE ROYAL SOCIETY A-MATHEMATICAL PHYSICAL AND ENGINEERING SCIENCES, 1991, 335 (1639): : 609 - 634
  • [2] Calculations of solution energies of fission products in uranium dioxide
    Grimes, R.W., 1856, Pharmacotherapy Publications Inc. (72):
  • [4] THERMODYNAMICS OF THE SYSTEM URANIUM DIOXIDE FISSION PRODUCTS ZIRCALOY
    KOHLI, R
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 33 (NOV): : 281 - 282
  • [5] FISSION PRODUCTS AND PLUTONIUM MIGRATE IN URANIUM-DIOXIDE FUEL
    BATES, JL
    ROAKE, WE
    CHRISTENSEN, JA
    NUCLEONICS, 1962, 20 (03): : 88 - &
  • [6] CALCULATIONS OF SOLUTION ENERGIES OF FISSION-PRODUCTS IN URANIUM-DIOXIDE
    GRIMES, RW
    CATLOW, CRA
    STONEHAM, AM
    JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1989, 72 (10) : 1856 - 1860
  • [7] Modeling the diffusion yield of radioactive fission products from uranium dioxide fuel
    Tarasov, V. I.
    ATOMIC ENERGY, 2009, 106 (06) : 395 - 408
  • [8] Swelling due to fission products and additives dissolved within the uranium dioxide lattice
    Middleburgh, S. C.
    Grimes, R. W.
    Desai, K. H.
    Blair, P. R.
    Hallstadius, L.
    Backman, K.
    Van Uffelen, P.
    JOURNAL OF NUCLEAR MATERIALS, 2012, 427 (1-3) : 359 - 363
  • [9] SEPARATION OF FISSION PRODUCTS FROM IRRADIATED URANIUM DIOXIDE IN FUSED NITRATE SYSTEMS
    YAMAGISHI, S
    KAMEMOTO, Y
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY-TOKYO, 1965, 2 (11): : 457 - +
  • [10] Modeling the diffusion yield of radioactive fission products from uranium dioxide fuel
    V. I. Tarasov
    Atomic Energy, 2009, 106 : 395 - 408