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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2019.6
- 수록면
- 58 - 68 (11page)
- DOI
- 10.6112/kscfe.2019.24.2.058
이용수
초록· 키워드
오류제보하기
The Korea Atomic Energy Research Institute (KAERI) has performed a reactor design with the final goal of constructing the PGSFR (Prototype Gen-IV Sodium-cooled Fast Reactor). The main objective of the PGSFR is to verify TRU metal fuel performance, reactor operation, and transmutation ability of high-level wastes. In the PGSFR, each subassembly has an independent flow path and is separately assigned a flow rate. Therefore, outlet temperatures between adjacent subassemblies are different from each other. Coolant mixing with different temperatures causes temperature fluctuations in a structure surface near the core exit. This phenomenon is called thermal striping, which can induce periodic thermal fatigues and deteriorate the integrity of the structures. The thermal striping in the UIS (upper internal structure) of the PGSFR is evaluated by the LES model. This model is employed to characterize fast turbulent vortices generated from the core exit. Temperature fluctuation is observed along a mixing region between two adjacent assemblies. The maximum temperature fluctuation on the solid surface occurs at the CRDM guide tube tip of the outer control assembly in the core outward direction. The maximum RMS value of the temperature fluctuation at the solid surface is 18.3% of the temperature difference. The present CFD analysis will be employed to evaluate creep-fatigue damage due to the temperature fluctuation cycles in the UIS.
목차
1. 서론
2. 수치해석 방법
3. 열스트라이핑 해석조건
4. 해석결과
5. 결론
References
참고문헌 (12)
참고문헌 신청
2016, Yoo, J., Chang, J., Lim, J.Y., Cheon, J.S., Lee, T.H., Kim, S.K., Lee, K.L. and Joo, H.K.., Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea, Nuclear Engineering and Technology, Vol.48, pp.1059-1070.
2009, Chellapandi, P., Chetal, S.C. and Raj, B., Thermal Striping Limits for Components of Sodium Cooled Fast Spectrum Reactors, Nuclear Engineering and Design, Vol.239, pp.2754-2765.
2004, Nam, H.Y. and Kim, J.M., Thermal Striping Experimental Data, Korea Atomic Energy Research Institute, Internal Design Report, LMR/IOC-ST-002-04-Rev.0/04.
2009, Kobayashi, J., Kimura, N., Tobita, A., Kamide, H., Watanabe, A. and Ohyama, K., Study on Thermal Striping at UIS of Advanced Loop Type Fast Reactor, ICONE17, Brussels, Belgium.
2006, Velusamy, K., Natesan, K., Selvaraj, P., Chellapandi, P., Chetal, S.C., Sundararajan, T. and Suyambazhahan, S., CFD Studies in the Prediction of Themral Striping in an LMFBR, CFD4NRS, Garching, Munich.
2009, Chellapandi, P., Chetal, S.C. and Raj, B., Thermal Striping Limits for Components of Sodium Cooled Fast Spectrum Reactors, Nuclear Engineering and Design, Vol.239, pp.2754-2765.
2004, Nam, H.Y. and Kim, J.M., Thermal Striping Experimental Data, Korea Atomic Energy Research Institute, Internal Design Report, LMR/IOC-ST-002-04-Rev.0/04.
2009, Kobayashi, J., Kimura, N., Tobita, A., Kamide, H., Watanabe, A. and Ohyama, K., Study on Thermal Striping at UIS of Advanced Loop Type Fast Reactor, ICONE17, Brussels, Belgium.
2006, Velusamy, K., Natesan, K., Selvaraj, P., Chellapandi, P., Chetal, S.C., Sundararajan, T. and Suyambazhahan, S., CFD Studies in the Prediction of Themral Striping in an LMFBR, CFD4NRS, Garching, Munich.
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UCI(KEPA) : I410-ECN-0101-2019-559-000869528