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Characterization of Cement Solidification for Enhancement of Cesium Leaching Resistance KCI 등재 SCOPUS

세슘 침출 저항성 증진 시멘트 고화체의 제조 및 특성 평가

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

Currently, the Korea Atomic Energy Research Institute (KAERI) is planning to build the Ki-Jang Research Reactor (KJRR) in Ki-Jang, Busan. It is important to safely dispose of low-level radioactive waste from the operation of the reactor. The most efficient way to treat radioactive waste is cement solidification. For a radioactive waste disposal facility, cement solidification is performed based on specific waste acceptance criteria such as compressive strength, free-standing water, immersion and leaching tests. Above all, the leaching test is important to final disposal. The leakage of radioactive waste such as 137Cs causes not only regional problems but also serious global ones. The cement solidification method is simple, and cheaper than other solidification methods, but has a lower leaching resistance. Thus, this study was focused on the development of cement solidification for an enhancement of cesium leaching resistance. We used Zeolite and Loess to improve the cesium leaching resistance of KJRR cement solidification containing simulated KJRR liquid waste. Based on an SEM-EDS spectrum analysis, we confirmed that Zeolite and Loess successfully isolated KJRR cement solidification. A leaching test was carried out according to the ANS 16.1 test method. The ANS 16.1 test is performed to analyze cesium ion concentration in leachate of KJRR cement for 90 days. Thus, a leaching test was carried out using simulated KJRR liquid waste containing 3000 mg·L-1 of cesium for 90 days. KJRR cement solidification with Zeolite and Loess led to cesium leaching resistance values that were 27.90% and 21.08% higher than the control values. In addition, in several tests such as free-standing water, compressive strength, immersion, and leaching tests, all KJRR cement solidification met the waste acceptance or satisfied the waste acceptance criteria for final disposal.

목차
1. 서론
 2. 실험
  2.1 실험재료
  2.2 실험방법
 3. 결과 및 논의
  3.1 시멘트 고화체 제조 및 특성평가
  3.2 시멘트 고화체 안정성 평가
  3.3 압축강도 측정
 4. 결론
 REFERENCES
저자
  • Gi Yong Kim(Korea Atomic Energy Research Institute) | 김지용
  • Won-Hyuk Jang(Korea Atomic Energy Research Institute) | 장원혁
  • Sung-Chan Jang(Advanced Radiation Technology Institute) | 장성찬
  • Junhyuck Im(Korea Atomic Energy Research Institute) | 임준혁
  • Dae Seok Hong(Korea Atomic Energy Research Institute) | 홍대석
  • Chel Gyo Seo(Korea Atomic Energy Research Institute) | 서철교
  • Jong Sik Shon(Korea Atomic Energy Research Institute,) | 손종식 Corresponding Author