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The Effect of Turbulence Penetration on the Thermal Stratification Phenomenon Caused by Leaking Flow in a T-Branch of Square Cross-Section  

홍석우 (고려대학교 대학원)
최영돈 (고려대학교 기계공학과)
박민수 (고려대학교 대학원)
Publication Information
Korean Journal of Air-Conditioning and Refrigeration Engineering / v.15, no.3, 2003 , pp. 239-245 More about this Journal
Abstract
In the nuclear power plant, emergency core coolant system (ECCS) is furnished at reactor coolant system (RCS) in order to cool down high temperature water in case of emergency. However, in this coolant system, thermal stratification phenomenon can occur due to coolant leaking in the check valve. The thermal stratification produces excessive thermal stresses at the pipe wall so as to yield thermal fatigue crack (TFC) accident. In the present study, effects of turbulence penetration on the thermal stratification into T-branches with square cross-section in the modeled ECCS are analysed numerically. $textsc{k}$-$\varepsilon$ model is employed to calculate the Reynolds stresses in momentum equations. Results show that the length and strength of thermal stratification are primarily affected by the leak flow rate of coolant and the Reynolds number of the main flow in the duct. Turbulence penetration into the T-branch of ECCS shows two counteracting effects on the thermal stratification. Heat transport by turbulence penetration from the main duct to leaking flow region may enhance thermal stratification while the turbulent diffusion may weaken it.
Keywords
Thermal stratification; Turbulence penetration; T branch; Emergency core coolant system;
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  • Reference
1 /
[] / Steam Generator FeedWater Distribution Piping Damage(NRC, Information Notice No. 91-19)
2 /
[ EPRI ] / Thermal Stratification, Cycling and Striping(TASCS), TR-103581
3 Numerical study on the thermal mixing flow of cold lef during high pressure safety injection after loss of coolant accident /
[ Park, M. H.;Kim, K. C.;Noh, H. K.;Kim, K. H. ] / Proc. of the First National Congress in Fluids Engineering
4 Safety analysis on fatigue cracking of pressurizer nozzle in nuclear power plant /
[ Han, K. S.;Kim, S. T.;Park, K. S.;Jang, K. S.;Choi, S. N. ] / Proc. of the Korea Society of Mechanical Engineers
5 /
[] / Pressurizer surge line Thermal Stratification(NRC Bulletin 88-11)
6 /
[] / Thermal Stress in Piping Connected to Reactor Coolant System(NRC Bulletin 88-08)
7 Accessment of internal leakage and temperature watching of pressure waring value /
[ Park, Joon Hyuk;Chung, Il Seok ] / Proc. of 99 Fall Conferance