Slipcasting of MAX phase tubes for nuclear fuel cladding applications

被引:16
|
作者
Galvin, T. [1 ]
Hyatt, N. C. [1 ]
Rainforth, W. M. [1 ]
Reaney, I. M. [1 ]
Shepherd, D. [2 ]
机构
[1] Univ Sheffield, Dept Mat Sci & Engn, Sir Robert Hadfield Bldg,Mappin St, Sheffield S1 3JD, S Yorkshire, England
[2] NNL, NNL Preston Lab, Preston PR4 0XJ, Lancs, England
基金
英国工程与自然科学研究理事会;
关键词
MAX phase; Slipcast; Nuclear fuel; Clad; Ti3SiC2; NEUTRON-IRRADIATION; TI3SIC2; TI3ALC2; TI2ALC; OXIDATION; CORROSION; EVOLUTION; BEHAVIOR; CR2ALC;
D O I
10.1016/j.nme.2020.100725
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
As a proof of concept, tubes of Ti3SiC2 MAX phase were slipcast in order to investigate its potential for the fabrication of fuel cladding for nuclear reactors. A slip consisting of 46% dry weight basis (dwb) water, 4% dwb polyethyleneimine (PEI), 0.5% dwb methylcellulose was used to cast the tubes, which were then sintered for 2 h under vacuum at 1450 degrees C. Silicon loss was observed at surface which resulted in the formation of TiC. The hoop stress to destruction of the tubes was measured and achieved a maximum of 9.1 +/- 2.2 MPa/mm of tube thickness.
引用
收藏
页数:8
相关论文
共 50 条
  • [1] Infrared observation of ballooning and burst of nuclear fuel cladding tubes
    Nagy, Richard
    Kir, Marton
    Petrik, Peter
    Hozer, Zoltan
    NUCLEAR ENGINEERING AND DESIGN, 2021, 371
  • [2] Creep Tests Research on a New Zirconium Alloy for Nuclear Fuel Cladding Tubes
    Meng, Xinming
    Xue, Fei
    Yu, Weiwei
    Guo, Hongmei
    NEW TRENDS IN MECHATRONICS AND MATERIALS ENGINEERING, 2012, 151 : 47 - +
  • [3] Multiaxial Plastic Deformation of Zircaloy-4 Nuclear Fuel Cladding Tubes
    Kamerman, David
    Nelson, Malachi
    NUCLEAR TECHNOLOGY, 2023, 209 (06) : 872 - 886
  • [4] Acid Dissolution Behavior of Ferritic FeCrAl Tubes Candidates for Nuclear Fuel Cladding
    Rebak, Raul B.
    Yin, Liang
    Jurewicz, Timothy B.
    Hoffman, Andrew K.
    CORROSION, 2021, 77 (12) : 1321 - 1331
  • [5] Structure of the pellet-cladding interaction layer of a high-burnup Zr-Nb-O nuclear fuel cladding
    Liu, Xiang
    Cinbiz, Mahmut Nedim
    Kombaiah, Boopathy
    He, Lingfeng
    Teng, Fei
    Lacroix, Evrard
    JOURNAL OF NUCLEAR MATERIALS, 2021, 556
  • [6] Radiation response of Ti2AlC MAX phase coated Zircaloy-4 for accident tolerant fuel cladding
    Gigax, Jonathan G.
    Kennas, Miltiadis
    Kim, Hyosim
    Wang, Tianyao
    Maier, Benjamin R.
    Yeom, Hwasung
    Johnson, Greg O.
    Sridharan, Kumar
    Shao, Lin
    JOURNAL OF NUCLEAR MATERIALS, 2019, 523 : 26 - 32
  • [7] Structure of the fuel-cladding chemical interaction (FCCI) layer of a high burnup Zr-1Nb nuclear fuel cladding
    Song, Wulin
    Han, Xue
    Cheng, Huanlin
    Tang, Qi
    Wang, Huacai
    Ji, Songtao
    JOURNAL OF NUCLEAR MATERIALS, 2025, 607
  • [8] Reassessment of oxidation-induced amorphization and dissolution of Nb precipitates in Zr-Nb nuclear fuel cladding tubes
    Matsukawa, Y.
    Kitayama, S.
    Murakami, K.
    Shinohara, Y.
    Yoshida, K.
    Maeno, H.
    Yang, H. L.
    Toyama, T.
    Yasuda, K.
    Watanabe, H.
    Kimura, A.
    Muta, H.
    Yamanaka, S.
    Li, Y. F.
    Satoh, Y.
    Kano, S.
    Abe, H.
    ACTA MATERIALIA, 2017, 127 : 153 - 164
  • [9] Zirconium surface modification under fission product irradiation.: Application to nuclear fuel cladding tubes
    Bérerd, N
    Catalette, H
    Chevarier, A
    Chevarier, N
    Faust, H
    Moncoffre, N
    SURFACE & COATINGS TECHNOLOGY, 2002, 158 : 473 - 476
  • [10] Enhanced accident tolerance properties of AlCrCuFeMoNbx high entropy coating for nuclear fuel cladding
    Zhu, Yayan
    Tao, Zhenrui
    Gu, Xiaoyan
    Wang, Chunji
    Lan, Rui
    JOURNAL OF ALLOYS AND COMPOUNDS, 2025, 1010