과제정보
본 연구는 한국에너지기술평가원 재원으로, 원전 안전운영을 위한 핵심소재, 부품, 장비 국산화 기술개발사업 '사용후핵연료 연소도 측정 설비 기술개발(과제번호: 20222B10100060)'에 의해 수행되었으며, 그 지원에 감사드립니다.
참고문헌
- Kim TY, Park HM, Song YS and Lee UJ. 2022. Study on the decontamination of cs-137 and sr-90 contained in the liquid radioactive waste discharged from the spent fuel storage tank using microalgae. Resources Recycling 31(5):20-25. https://doi.org/10.7844/kirr.2022.31.5.20
- Lee SH, Kim SH, Shin CM and Jung HR. 2022. Evaluation of thermal and structural properties of spent nuclear fuel disposal system with different canister materials. J. Radiat. Ind. 16(4):473-483. https://doi.org/10.23042/radin.2022.16.4.473
- Park SH, Eom SH, Shin HS, Lim HI, Ha JH and Kim HS. 2010. Fabrication of ionization chamber to measure the burnup of spent fuel. J. Radiat. Prot. Res. 35(1):21-25. CI:G704-001034.2010.35.1.004
- Kim HG, Hong YH, Jung YS, Kim, Kim JH and Park SY. 2020. Development of a portable detection system for simultaneous measurements of neutrons and gamma rays. J. Radiol. Sci. Technol. 43(6):481-487. https://doi.org/10.17946/JRST.2020.43.6.481
- Knoll GF. 2000. Radiation detection and measurement. 3th ed. pp. 326-329. John Wiley & Sons, Inc. New York.