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

Abstract

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-10 wt.%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-10 wt.%Zr fuel slugs with a diameter of 5.5 mm. Consequently, fuel slugs per melting 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.

Authors:
 [1]; ORCiD logo [1];  [1];  [1];  [1];  [1]
  1. Next Generation Fuel Division, Korea Atomic Energy Research Institute, Daejeon 305-353, Republic of Korea
Publication Date:
Sponsoring Org.:
USDOE
OSTI Identifier:
1328446
Resource Type:
Published Article
Journal Name:
Science and Technology of Nuclear Installations
Additional Journal Information:
Journal Name: Science and Technology of Nuclear Installations Journal Volume: 2016; Journal ID: ISSN 1687-6075
Publisher:
Hindawi Publishing Corporation
Country of Publication:
Egypt
Language:
English

Citation Formats

Kim, Ki-Hwan, Kim, Jong-Hwan, Oh, Seok-Jin, Lee, Jung-Won, Lee, Ho-Jin, and Lee, Chan-Bock. Fabrication of U-10 wt.%Zr Metallic Fuel Rodlets for Irradiation Test in BOR-60 Fast Reactor. Egypt: N. p., 2016. Web. doi:10.1155/2016/4385925.
Kim, Ki-Hwan, Kim, Jong-Hwan, Oh, Seok-Jin, Lee, Jung-Won, Lee, Ho-Jin, & Lee, Chan-Bock. Fabrication of U-10 wt.%Zr Metallic Fuel Rodlets for Irradiation Test in BOR-60 Fast Reactor. Egypt. https://doi.org/10.1155/2016/4385925
Kim, Ki-Hwan, Kim, Jong-Hwan, Oh, Seok-Jin, Lee, Jung-Won, Lee, Ho-Jin, and Lee, Chan-Bock. Fri . "Fabrication of U-10 wt.%Zr Metallic Fuel Rodlets for Irradiation Test in BOR-60 Fast Reactor". Egypt. https://doi.org/10.1155/2016/4385925.
@article{osti_1328446,
title = {Fabrication of U-10 wt.%Zr Metallic Fuel Rodlets for Irradiation Test in BOR-60 Fast Reactor},
author = {Kim, Ki-Hwan and Kim, Jong-Hwan and Oh, Seok-Jin and Lee, Jung-Won and Lee, Ho-Jin and Lee, Chan-Bock},
abstractNote = {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-10 wt.%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-10 wt.%Zr fuel slugs with a diameter of 5.5 mm. Consequently, fuel slugs per melting 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.},
doi = {10.1155/2016/4385925},
journal = {Science and Technology of Nuclear Installations},
number = ,
volume = 2016,
place = {Egypt},
year = {Fri Jan 01 00:00:00 EST 2016},
month = {Fri Jan 01 00:00:00 EST 2016}
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record
https://doi.org/10.1155/2016/4385925

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Cited by: 4 works
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Works referenced in this record:

History of fast reactor fuel development
journal, September 1993


Fuels for sodium-cooled fast reactors: US perspective
journal, September 2007

  • Crawford, Douglas C.; Porter, Douglas L.; Hayes, Steven L.
  • Journal of Nuclear Materials, Vol. 371, Issue 1-3
  • DOI: 10.1016/j.jnucmat.2007.05.010

Metallic fast reactor fuels
journal, January 1997


Current Status of Pyroprocessing Development at KAERI
journal, January 2013

  • Lee, Hansoo; Park, Geun-IL; Lee, Jae-Won
  • Science and Technology of Nuclear Installations, Vol. 2013
  • DOI: 10.1155/2013/343492

Protective yttria coatings of melting crucible for metallic fuel slugs: Protective yttria coatings of melting crucible for metallic fuel slugs
journal, December 2014

  • Kim, Jong-Hwan; Song, Hoon; Kim, Ki-Hwan
  • Surface and Interface Analysis, Vol. 47, Issue 3
  • DOI: 10.1002/sia.5703

Microstructural characterization of U-Zr alloy fuel slugs for sodium-cooled fast reactor: Microstructural characterization of U-Zr alloy fuel slugs
journal, June 2012

  • Kim, Ki-Hwan; Oh, Seok-Jin; Kim, Sun-Ki
  • Surface and Interface Analysis, Vol. 44, Issue 11-12
  • DOI: 10.1002/sia.4989

Development of continuous ingot casting process for uranium dendrites in pyroprocess
journal, August 2012

  • Jang, Jun-Hyuk; Kang, Hee-Seok; Lee, Yun-Sang
  • Journal of Radioanalytical and Nuclear Chemistry, Vol. 295, Issue 3
  • DOI: 10.1007/s10967-012-2093-3

Preparation of U–Zr–Mn, a Surrogate Alloy for Recycling Fast Reactor Fuel
journal, January 2015

  • Kim, Jong-Hwan; Kim, Ki-Hwan; Lee, Chan-Bock
  • Advances in Materials Science and Engineering, Vol. 2015
  • DOI: 10.1155/2015/131704

Generation-IV nuclear power: A review of the state of the science
journal, December 2008


Uranium Enrichment Reduction in the Prototype Gen-IV Sodium-Cooled Fast Reactor (PGSFR) with PBO Reflector
journal, April 2016

  • Kim, Chihyung; Hartanto, Donny; Kim, Yonghee
  • Nuclear Engineering and Technology, Vol. 48, Issue 2
  • DOI: 10.1016/j.net.2016.01.005

Effect of Heat on the Soundness of Zircaloy-4 End Cap Closure Using a Resistance Upset Welding
journal, January 2010

  • Kim, Soo-Sung; Park, Geun-Il; Lee, Jung-Won
  • Journal of Nuclear Science and Technology, Vol. 47, Issue 3
  • DOI: 10.3327/jnst.47.262

Magnesium alloys and applications
journal, January 1994


Pyroprocessing Technology Development at Kaeri
journal, August 2011

  • Lee, Han-Soo; Park, Geun-Il; Kang, Kweon-Ho
  • Nuclear Engineering and Technology, Vol. 43, Issue 4
  • DOI: 10.5516/NET.2011.43.4.317

Electrodeposition characteristics of uranium by using a graphite cathode
journal, November 2006