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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2022.4
- 수록면
- 1,343 - 1,354 (12page)
- DOI
- https://doi.org/10.1016/j.net.2021.10.008
이용수
초록· 키워드
오류제보하기
Experiments were performed to measure the critical heat flux (CHF) on a vertical surface abutting acoarse packed bed of spherical particles. This geometry is representative of a CANDU reactor calandriatubesheet facing the end shield cavity during the in-vessel retention (IVR) phase of a severe accident.
Deionized light water was used as the working fluid. Low carbon steel shielding balls with diametersranging from 6.4 to 12.7 mm were used, allowing for the development of an empirical correlation of CHFas a function of shielding ball diameter. Previously published data is used to develop a more comprehensive empirical correlation accounting for the impacts of both shielding ball diameter and heatingsurface height. Tests using borosilicate shielding balls demonstrated that the dependence of CHF onshielding ball thermal conductivity is insignificant. The deposition of iron oxide particles transportedfrom shielding balls to the heating surface is verified to increase CHF non-trivially. The results presentedin this paper improve the state of the knowledge base permitting quantitative prediction of CHF in theCANDU end shield, refining our ability to assess the feasibility of IVR. The findings clarify the mechanismsgoverning CHF in this scenario, permitting identification of potential future research directions.
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