중·저준위 방사성 폐기물 처분을 위한 원전해체 재생시멘트의 고화재로서의 사용성 평가
- Alternative Title
- Evaluation of Recycled Cement Powder Obtained from Nuclear Power Plant as a Solidifying Agent for Low and Intermediate Radioactive Waste Immobilization
- Abstract
- During decommissioning of nuclear power plants, a significant amount of concrete waste is generated. In most cases, all radioactive waste must be stored in a designated disposal facility. For such purpose, radioactive wastes are solidified using cement to prevent leakage of any radioactive elements into the environment. This study aims to assess the viability of recycling irradiated cement paste obtained from concrete in nuclear power plant as a solidifying agent, and thus ultimately reducing the volume of overall concrete waste generated during decommissioning process. To make simulated irradiated cement paste that can be obtained from concrete in decommissioned nuclear power plants, cement paste aged for 2 years was crushed into powder whose size was below 150㎛. To recover its hydraulic reactivity, heat treatment at 500℃, 600℃, and 700℃ for 2 hours were applied. Obtained recycled cement powder was mixed with liquid waste simulants such as 1M solutions of CoCl2, CsCl, and SrCl2, to make wasteform specimens. The 28 day compressive strength, thermal cycling, and leachabilities of Co, Cs, and Sr were measured in accordance with the solidification acceptance criteria set by the Nuclear Regulatory Commission(NRC). Set time and heat of hydration were also measured to understand fundamental characteristics of recycled cement powder. According to the results, specimens made of liquid waste simulants set much faster than specimens made of deionized water. Recycled cement powder, treated at 500℃ showed lower heat of hydration than that treated at higher temperatures. This means 500℃ is not an optimum temperature that can produce necessary reactivity. Recycled cement powders, treated at 600℃ and 700℃, did not show noticeable difference in terms of wasteform performance, meaning that 600℃ is better economical/environmental option for heat treatment. All wasteform specimens met the solidification acceptance criteria, and notably, the leaching test surpassed the standards, showing remarkable stability. This implies the feasibility of utilizing irradiated recycled cement powder as a solidifying agent for immobilization of low and intermediate level radioactive wastes.
- Author(s)
- 최유진
- Issued Date
- 2024
- Awarded Date
- 2024-02
- Type
- Dissertation
- Keyword
- recycled cement, radioactive waste immobilization, solidifying agent
- Publisher
- 국립부경대학교 대학원
- URI
- https://repository.pknu.ac.kr:8443/handle/2021.oak/33785
http://pknu.dcollection.net/common/orgView/200000743432
- Alternative Author(s)
- Choi Yujin
- Affiliation
- 국립부경대학교 대학원
- Department
- 대학원 건축·소방공학부
- Advisor
- 정철우
- Table Of Contents
- I. 서 론 1
1.1 연구의 배경 및 목적 1
1.2 연구의 방법 및 범위 4
II. 이론적 고찰 7
2.1 방사성 폐기물의 분류 7
2.2 방사성 폐기물의 처리 · 11
2.3 핵종의 고정화 13
2.4 재생시멘트 15
2.5 온도 구간별 탈수화반응 18
2.6 폐기물 고화체의 인수기준 21
2.7 방사성 핵종의 종류 및 농도 · 23
III. 실험계획 27
3.1 실험재료 · 27
3.1.1 재생시멘트의 제작 및 분석 27
3.1.2 수용액의 제조 32
3.1.3 시멘트 · 32
3.2 시험체의 제작 34
3.3 실험방법 · 37
IV. 실험결과 및 고찰 43
4.1 응결·경화 시간(set time) · 43
4.2 수화열(heat of hydration) 46
4.3 압축강도 및 밀도(compressive strength and density) 49
4.4 열순환(thermal cycle) · 51
4.5 침출 및 침지(laeching and immersion) 53
Ⅴ. 결 론 56
Ⅵ. 부 록 58
6.1 미소수화열 58
6.2 고화체의 종결시간 특성 61
참 고 문 헌 · 62
- Degree
- Master
-
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- 대학원 > 건축소방공학부
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