Fabrication of U-10 wt.% Zr Metallic Fuel Rodlets for Irradiation Test in BOR-60 Fast Reactor

被引:2
作者
Kim, Ki-Hwan [1 ]
Kim, Jong-Hwan [1 ]
Oh, Seok-Jin [1 ]
Lee, Jung-Won [1 ]
Lee, Ho-Jin [1 ]
Lee, Chan-Bock [1 ]
机构
[1] Korea Atom Energy Res Inst, Next Generat Fuel Div, Daejeon 305353, South Korea
关键词
URANIUM; ALLOY;
D O I
10.1155/2016/4385925
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
The fabrication technology for metallic fuel has been developed to produce the driver fuel in a PGSFR in Korea since 2007. In order to evaluate the irradiation integrity and validate the in-reactor of the starting metallic fuel with FMS cladding for the loading of the metallic fuel, U-10wt.% Zr fuel rodlets were fabricated and evaluated for a verification of the starting driver fuel through an irradiation test in the BOR-60 fast reactor. The injection casting method was applied to U-10wt.% Zr fuel slugs with a diameter of 5.5 mm. Consequently, fuel slugs permelting batch without casting defects were fabricated through the development of advanced casting technology and evaluation tests. The optimal GTAW welding conditions were also established through a number of experiments. In addition, a qualification test was carried out to prove the weld quality of the end plug welding of the metallic fuel rodlets. The wire wrapping of metallic fuel rodlets was successfully accomplished for the irradiation test. Thus, PGSFR fuel rodlets have been soundly fabricated for the irradiation test in a BOR-60 fast reactor.
引用
收藏
页数:7
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共 20 条
  • [1] Generation-IV nuclear power: A review of the state of the science
    Abram, Tim
    Ion, Sue
    [J]. ENERGY POLICY, 2008, 36 (12) : 4323 - 4330
  • [2] [Anonymous], 2002, TECHN ROADM GEN 4 NU
  • [3] Fuels for sodium-cooled fast reactors: US perspective
    Crawford, Douglas C.
    Porter, Douglas L.
    Hayes, Steven L.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2007, 371 (1-3) : 202 - 231
  • [4] Hofman G. L., 1997, Progress in Nuclear Energy, V31, P83, DOI 10.1016/0149-1970(96)00005-4
  • [5] IAEA and OECD, 2008, UR 2007 RES PROD DEM
  • [6] Ik-SooKim, 2003, Nuclear Engineering and Technology, V35, P309
  • [7] Development of continuous ingot casting process for uranium dendrites in pyroprocess
    Jang, Jun-Hyuk
    Kang, Hee-Seok
    Lee, Yun-Sang
    Lee, Hansoo
    Kim, Jeong-Guk
    [J]. JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, 2013, 295 (03) : 1743 - 1751
  • [8] Electrodeposition characteristics of uranium by using a graphite cathode
    Kang, Y. H.
    Lee, J. H.
    Hwang, S. C.
    Shim, J. B.
    Kim, E. H.
    Park, S. W.
    [J]. CARBON, 2006, 44 (14) : 3142 - 3145
  • [9] Uranium Enrichment Reduction in the Prototype Gen-IV Sodium-Cooled Fast Reactor (PGSFR) with PBO Reflector
    Kim, Chihyung
    Hartanto, Donny
    Kim, Yonghee
    [J]. NUCLEAR ENGINEERING AND TECHNOLOGY, 2016, 48 (02) : 351 - 359
  • [10] Preparation of U-Zr-Mn, a Surrogate Alloy for Recycling Fast Reactor Fuel
    Kim, Jong-Hwan
    Kim, Ki-Hwan
    Lee, Chan-Bock
    [J]. ADVANCES IN MATERIALS SCIENCE AND ENGINEERING, 2015, 2015