Distribution of fission products palladium, silver, cerium and cesium in the un-corroded areas of the locally corroded SiC layer of a neutron irradiated TRISO fuel particle

被引:10
作者
Wen, Haiming [1 ,2 ]
van Rooyen, Isabella J. [2 ]
机构
[1] Idaho State Univ, Dept Phys Nucl & Elect Engn, Idaho Falls, ID 83402 USA
[2] Idaho Natl Lab, Fuel Design & Dev Dept, Idaho Falls, ID 83415 USA
关键词
TRISO particle; Fission product; Transport mechanism; Neutron irradiation; Electron microscopy; CUBIC SILICON-CARBIDE; COATED PARTICLES; AGR-1; EXPERIMENT; AG TRANSPORT; REACTOR-FUEL; DIFFUSION; RELEASE; PD; PERFORMANCE; BEHAVIOR;
D O I
10.1016/j.jeurceramsoc.2017.04.012
中图分类号
TQ174 [陶瓷工业]; TB3 [工程材料学];
学科分类号
0805 ; 080502 ;
摘要
Detailed electron microscopy studies were performed to investigate distribution and composition of fission products in the SiC layer of a tristructural-isotropic-coated particle exhibiting localized corrosion. Previous studies on this particle indicated that pure carbon areas in the SiC layer, resulting from localized corrosion of SiC by Pd, provide pathways for Ag, Cd, and Cs migration. This study reveals the presence of Ag- and/or Cd-containing precipitates in un-corroded SiC areas. Ag and Cd may exist by themselves or coexist with Pd. Ag and Cd mainly transport along SiC grain boundaries. An Ag-Pd-Cd precipitate was identified at a stacking fault inside a SiC grain, suggesting that intragranular transport of Ag and Cd is possible. Ce is present with Pd or Pd-U in some precipitates. U and Ce frequently coexist, whereas Ag and Cd usually do not coexist with U or Ce. No Cs was detected in any precipitates in the areas examined. Published by Elsevier Ltd.
引用
收藏
页码:3271 / 3284
页数:14
相关论文
共 49 条
  • [1] DIFFUSION OF SILVER AND CESIUM IN SILICON-CARBIDE COATINGS OF FUEL-PARTICLES FOR HIGH-TEMPERATURE GAS-COOLED REACTORS
    AMIAN, W
    STOVER, D
    [J]. NUCLEAR TECHNOLOGY, 1983, 61 (03) : 475 - 486
  • [2] [Anonymous], ALL PHAS DIAGR DAT
  • [3] GRAIN-BOUNDARY DIFFUSION MECHANISMS IN METALS
    BALLUFFI, RW
    [J]. METALLURGICAL TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 1982, 13 (12): : 2069 - 2095
  • [4] Fission-product behaviour in irradiated TRISO-coated particles: Results of the HFR-EU1bis experiment and their interpretation
    Barrachin, M.
    Dubourg, R.
    de Groot, S.
    Kissane, M. P.
    Bakker, K.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2011, 415 (01) : 104 - 116
  • [5] Kinetic Monte Carlo (KMC) simulation of fission product silver transport through TRISO fuel particle
    de Bellefon, G. Meric
    Wirth, B. D.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2011, 413 (02) : 122 - 131
  • [6] Demkowicz P.A., 2012, P HTR 2012 C TOK JAP
  • [7] Irradiation performance of AGR-1 high temperature reactor fuel
    Demkowicz, Paul A.
    Hunn, John D.
    Ploger, Scott A.
    Morris, Robert N.
    Baldwin, Charles A.
    Harp, Jason M.
    Winston, Philip L.
    Gerczak, Tyler J.
    van Rooyen, Isabella J.
    Montgomery, Fred C.
    Silva, Chinthaka M.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2016, 306 : 2 - 13
  • [8] Engelhard J., 1975, NUCL ENG DES, P85
  • [9] Investigation of silver and iodine transport through silicon carbide layers prepared for nuclear fuel element cladding
    Friedland, E.
    van der Berg, N. G.
    Matherbe, J. B.
    Hancke, J. J.
    Barry, J.
    Wendler, E.
    Wesch, W.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2011, 410 (1-3) : 24 - 31
  • [10] Study of silver diffusion in silicon carbide
    Friedland, E.
    Malherbe, J. B.
    van der Berg, N. G.
    Hlatshwayo, T.
    Botha, A. J.
    Wendler, E.
    Wesch, W.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2009, 389 (02) : 326 - 331