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Characteristics of Vitrification Process and Vitrified Form for Radioactive Waste KCI 등재 SCOPUS

방사성폐기물 유리화 공정 및 유리고화체 특성

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방사성폐기물학회지 (Journal of the Korean Radioactive Waste Society)
한국방사성폐기물학회 (Korean Radioactive Waste Society)
초록

In order to vitrify the combustible dry active waste (DAW) generated from Korean Nuclear Power Plants, a glass formulation development based on waste composition was performed. A borosilicate glass, DG-2, was formulated to vitrify the DAW in an induction cold crucible melter (CCM). The processability, product performance, and volume reduction effect of the candidate glass were evaluated using a computer code and were measured experimentally in the laboratory and CCM. The glass viscosity and electrical conductivity as the process parameters were in the desired ranges. Start-up and maintaining glass melt of the candidate glass were favorable in the CCM. The product of the glass product such as chemical durability, phase stability, and density was satisfactory. The vitrification process using the candidate glass was also evaluated assuming that it was operated as economically as possible.

목차
Abstract   I. Introduction   II. Computer Modeling for Glass Formulation   III. Experlmental Methods   IV. Results and Discussion    1. Processability    2. Product Performance    3. Volume Reduction Effect   V. Conclusions   References
저자
  • Cheon-Woo Kim(원자력환경기술원) | 김천우
  • Ji-Yean Kim(원자력환경기술원) | 김지연
  • Jong-Rak Choi(원자력환경기술원) | 최종락
  • Pyung-Kook Ji(원자력환경기술원) | 지평국
  • Jong-Kil Park(원자력환경기술원) | 박종길
  • Sang-Woon Shin(원자력환경기술원) | 신상운
  • Jong-Hyun Ha(원자력환경기술원) | 하종현
  • Myung-Jae Song(원자력환경기술원) | 송명재