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Studies on the Physico-chemical Properties of Mixed Radioactive Waste Glass
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  • Studies on the Physico-chemical Properties of Mixed Radioactive Waste Glass
  • Studies on the Physico-chemical Properties of Mixed Radioactive Waste Glass
저자명
Kim. C.W.,Choi. J.R.,Ji. P.K.,Park. J.K.,Shin. S.W.,Ha. J.H.,Song. M.J.,Hwang. T.W.,Park. S.J.
간행물명
방사선방어학회지
권/호정보
2004년|29권 1호|pp.33-39 (7 pages)
발행정보
대한방사선방어학회
파일정보
정기간행물|ENG|
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기타
이 논문은 한국과학기술정보연구원과 논문 연계를 통해 무료로 제공되는 원문입니다.
서지반출

기타언어초록

In order to vitrify the W1 waste (ion-exchange resin(IER), zeolite, and dry active waste(DAW)) generated from Korean Nuclear Power Plants, a glass formulation development based on waste compositions and production rates was performed. A aluminoborosilicate glass, AG8W1, was formulated to vitrify the W1 waste in an induction cold crucible melter(CCM). The processability, product performance, and economics of the candidate glass were calculated 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 quality of the glass such as chemical durability, phase stability, etc. was satisfactory. The vitrification process using the candidate glass was also evaluated to be operated as economically as possible.