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Research Papers

Characteristics of Vitrification Process and Vitrified Form for Radioactive Waste

원문정보

방사성폐기물 유리화 공정 및 유리고화체 특성

Cheon-Woo Kim, Ji-Yean Kim, Jong-Rak Choi, Pyung-Kook Ji, Jong-Kil Park, Sang-Woon Shin, Jong-Hyun Ha, Myung-Jae Song

피인용수 : 0(자료제공 : 네이버학술정보)

초록

영어

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

저자정보

  • Cheon-Woo Kim 김천우. 원자력환경기술원
  • Ji-Yean Kim 김지연. 원자력환경기술원
  • Jong-Rak Choi 최종락. 원자력환경기술원
  • Pyung-Kook Ji 지평국. 원자력환경기술원
  • Jong-Kil Park 박종길. 원자력환경기술원
  • Sang-Woon Shin 신상운. 원자력환경기술원
  • Jong-Hyun Ha 하종현. 원자력환경기술원
  • Myung-Jae Song 송명재. 원자력환경기술원

참고문헌

자료제공 : 네이버학술정보

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