Development of a Continuous CVD Process for TRISO Coating of AGR Fuel

被引:0
|
作者
Keeley, Joseph T. [1 ]
Tomlin, Bruce L. [1 ]
Richardson, W. Clay [1 ]
Barnes, Charles [2 ]
Marshall, Douglas [2 ]
机构
[1] Babcock & Wilcox Nucl Operat Grp, POB 785, Lynchburg, VA 24505 USA
[2] Battelle Energy Alliance, Idaho Falls, ID 83415 USA
关键词
D O I
暂无
中图分类号
TH [机械、仪表工业];
学科分类号
0802 ;
摘要
As part of the Department of Energy's Advanced Gas Reactor Fuel program, Babcock & Wilcox is developing a fluidized bed chemical vapor deposition process to deposit a TRISO coating on UCO and UO2 kernels. These coated kernels will go into irradiation tests in the Advanced Test Reactor at Idaho National Laboratory. This paper reports on the development activities including the furnace design and the furnace runs made to qualify the coating process.
引用
收藏
页码:1 / +
页数:2
相关论文
共 50 条
  • [1] Ceramography of irradiated TRISO fuel from the AGR-2 experiment
    Rice, F. J.
    Stempien, J. D.
    Demkowicz, P. A.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2018, 329 : 73 - 81
  • [2] CONTINUOUS CVD PROCESS FOR COATING FILAMENTS WITH TANTALUM CARBIDE
    HEFFERNA.WJ
    AHMAD, I
    HASKELL, RW
    [J]. JOURNAL OF THE ELECTROCHEMICAL SOCIETY, 1973, 120 (08) : C248 - C248
  • [3] Properties of BN coating on SiC fiber by continuous CVD process
    Suzuki, M
    Tanaka, Y
    Inoue, Y
    Miyamoto, N
    Sato, M
    Goda, K
    [J]. ADVANCED SIC/SIC CERAMIC COMPOSITES: DEVELOPMENTS AND APPLICATIONS IN ENERGY SYSTEMS, 2002, 144 : 165 - 172
  • [4] Design and fabrication of an advanced TRISO fuel with ZrC coating
    Porter, Ian E.
    Knight, Travis W.
    Dulude, Michael C.
    Roberts, Elwyn
    Hobbs, Jim
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2013, 259 : 180 - 186
  • [5] Comparison of microstructural and micro-chemical evolutions in the irradiated fuel kernels of AGR-1 and AGR-2 TRISO fuel particles
    Fu, Zhenyu
    He, Lingfeng
    van Rooyen, Isabella J.
    Yang, Yong
    [J]. PROGRESS IN NUCLEAR ENERGY, 2024, 176
  • [6] Development and Test Results of Thermocouples Used in the TRISO-Fuel Irradiation Experiment AGR-5/6/7
    Palmer, A. J.
    Skifton, R. S.
    Haggard, D. C.
    Swank, W. D.
    Scervini, M.
    Hawkes, G. L.
    Pham, C. B. T.
    Checketts, T. L.
    [J]. NUCLEAR TECHNOLOGY, 2023, 209 (03) : 448 - 470
  • [7] Comparison of unirradiated and irradiated AGR-2 TRISO fuel particle oxidation response
    Skitt, Darren J.
    Seibert, Rachel L.
    Gerczak, Tyler J.
    Helmreich, Grant W.
    Burns, Zachary M.
    Hunn, John D.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2023, 580
  • [8] Direct Strength Evaluation of the CVD SiC Coating of TRISO Coated Fuel Particle with Micro Hemi Spherical Shell Configuration
    Lee, Hyeon Keun
    Kim, Do Kyung
    [J]. JOURNAL OF THE KOREAN CERAMIC SOCIETY, 2007, 44 (07) : 368 - 374
  • [9] Analysis of fission product distribution and composition in the TRISO layers of AGR-2 fuel
    Gerczak, Tyler J.
    Hunn, John D.
    Morris, Robert N.
    Montgomery, Fred C.
    Skitt, Darren J.
    Baldwin, Charles A.
    Dyer, John A.
    Eckhart, Brian D.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2020, 364
  • [10] Mechanical characteristics of SiC coating layer in TRISO fuel particles
    Hosemann, P.
    Martos, J. N.
    Frazer, D.
    Vasudevamurthy, G.
    Byun, T. S.
    Hunn, J. D.
    Jolly, B. C.
    Terrani, K.
    Okuniewski, M.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2013, 442 (1-3) : 133 - 142