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Logistical Simulation for Concrete Treatment Process in Decommissioning

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한국방사성폐기물학회 학술논문요약집 (Abstracts of Proceedings of the Korean Radioactive Wasts Society)
한국방사성폐기물학회 (Korean Radioactive Waste Society)
목차
1. Introduction
2. Literature Review
    2.1 Concrete Properties
    2.2 Decontamination of Radionuclide
3. Application of Technology
    3.1 Pretreatment of concrete building
    3.2 Classification by concrete component
4. Simulation
    4.1 Assumptions in Simulation Modeling
    4.2 Input Data
    4.3. Simulation Model
5. Conclusion
ACKNOWLEDGEMENT
저자
  • Chang-Lak Kim(KEPCO International Nuclear Graduate School 658-91 Haemaji-ro, Seosaeng-myeon, Ulju-gun, Ulsan, Republic of Korea)
  • David Kessel(KEPCO International Nuclear Graduate School 658-91 Haemaji-ro, Seosaeng-myeon, Ulju-gun, Ulsan, Republic of Korea)
  • Bong-su Yoon(KEPCO International Nuclear Graduate School 658-91 Haemaji-ro, Seosaeng-myeon, Ulju-gun, Ulsan, Republic of Korea)