• 제목/요약/키워드: Irradiation test

검색결과 681건 처리시간 0.032초

3D 프린팅용 UV 경화 수지의 조사량 및 항온수조 침적에 따른 수축률의 차이 (Difference between shrinkage rate of irradiation amount of 3D printing UV curable resin and shrinkage rate according to a constant temperature water bath)

  • 김동연
    • 대한치과기공학회지
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    • 제42권2호
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    • pp.113-120
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    • 2020

  • Purpose: This study is to compare and analyze the shrinkage of the specimen after UV irradiation of UV cured resin at 5, 15, and 30 minutes. Methods: A cylindrical UV cured specimen was produced using a stainless steel mold. UV cured resin specimens were prepared in three groups: 5 minutes cured (5M), 15 minutes cured (15M), and 30 minutes cured (30M). The measurement was made in total 3rd. The measurement was made in total 3rd. The primary measurement was made after 24 hours using a digital measuring instrument. The 2nd and 3rd measurements were deposited in a constant temperature water bath and the shrinkage was measured. The measured data was calculated by referring to the ASTM C326 linear measurement calculation method. T-test and One-way ANOVA were performed to test the significance between groups. The post-test was conducted with Tukey (α=0.05). Results: When the inner diameter and the outer diameter of the three groups not placed in the water bath were compared and analyzed, the contraction was the smallest at 6.8% in the 5M group, and the contraction was the largest at 7.3% in the 30M group. In the outer diameter, the contraction of the 5M group was the smallest at 3.5%, and the contraction of the 30M group was the largest at 4.5%. Shrinkage decreased in all three groups immersed in a water bath for 3-7 days. Conclusion: In the UV cured resin specimen, the shrinkage increased as the amount of UV irradiation increased.

  • https://doi.org/10.14347/kadt.2020.42.2.113 인용 PDF KSCI

Development status of microcell UO2 pellet for accident-tolerant fuel

  • Kim, Dong-Joo;Kim, Keon Sik;Kim, Dong Seok;Oh, Jang Soo;Kim, Jong Hun;Yang, Jae Ho;Koo, Yang-Hyun
    • Nuclear Engineering and Technology
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    • 제50권2호
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    • pp.253-258
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    • 2018

  • A microcell $UO_2$ pellet, as an accident-tolerant fuel pellet, is being developed to enhance the accident tolerance of nuclear fuels under accident conditions as well as the fuel performance under normal operation conditions. Improved capture-ability for highly radioactive and corrosive fission product (Cs and I) is the distinct feature of a ceramic microcell $UO_2$ pellet, and the enhanced pellet thermal conductivity is that of a metallic microcell $UO_2$ pellet. The fuel temperature can be effectively decreased by enhanced thermal conductivity. In this study, the material concepts of metallic and ceramic microcell $UO_2$ pellets were designed, and the fabrication process of microcell $UO_2$ pellets embodying the designed concept was developed. We successfully implemented the microcell $UO_2$ pellets and produced microcell $UO_2$ pellets. In addition, an assessment of the out-of-pile properties of a microcell $UO_2$ pellet was performed, and the in-reactor performance and behavior of the developed microcell pellets were evaluated through a Halden irradiation test. According to the expectations, the excellent performance of the microcell $UO_2$ pellets was confirmed by the online measurement data of the Halden irradiation test.

  • https://doi.org/10.1016/j.net.2017.12.008 인용 PDF KSCI