Nuclear Engineering and Technology

  • 제49권4호
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  • Pages.734-743
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  • 2017
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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A Concise Design for the Irradiation of U-10Zr Metallic Fuel at a Very Low Burnup

  • Guo, Haibing (Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics) ;
  • Zhou, Wei (Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics) ;
  • Sun, Yong (Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics) ;
  • Qian, Dazhi (Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics) ;
  • Ma, Jimin (Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics) ;
  • Leng, Jun (Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics) ;
  • Huo, Heyong (Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics) ;
  • Wang, Shaohua (Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics)
  • 투고 : 2016.04.25
  • 심사 : 2016.12.07
  • 발행 : 2017.08.25
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초록

In order to investigate the swelling behavior and fuel-cladding interaction mechanism of U-10Zr alloy metallic fuel at very low burnup, an irradiation experiment was concisely designed and conducted on the China Mianyang Research Reactor. Two types of irradiation samples were designed for studying free swelling without restraint and the fuel-cladding interaction mechanism. A new bonding material, namely, pure aluminum powder, was used to fill the gap between the fuel slug and sample shell for reducing thermal resistance and allowing the expansion of the fuel slug. In this paper, the concise irradiation rig design is introduced, and the neutronic and thermal-hydraulic analyses, which were carried out mainly using MCNP (Monte Carlo N-Particle) and FLUENT codes, are presented. Out-of-pile tests were conducted prior to irradiation to verify the manufacturing quality and hydraulic performance of the rig. Nondestructive postirradiation examinations using cold neutron radiography technology were conducted to check fuel cladding integrity and swelling behavior. The results of the preliminary examinations confirmed the safety and effectiveness of the design.

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참고문헌

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