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http://dx.doi.org/10.5516/NET.2009.41.3.287

SIMULATION OF THERMAL STRATIFICATION IN INLET NOZZLE OF STEAM GENERATOR  

Ji, Joon-Suk (Nuclear Engr, Dept., Kyung Hee Univ.)
Youn, Bum-Su (Nuclear Engr, Dept., Kyung Hee Univ.)
Jeong, Hyun-Chul (Nuclear Engr, Dept., Kyung Hee Univ.)
Kim, Sang-Nyung (Nuclear Engr, Dept., Kyung Hee Univ.)
Publication Information
Nuclear Engineering and Technology / v.41, no.3, 2009 , pp. 287-294 More about this Journal
Abstract
Due to thermal hydraulics phenomena, such as thermal stratification, various events occur to the parts of a nuclear power plant during their lifetimes: e.g. cracked and dislocated pipes and thermally fatigued, bent, and damaged supports. Due to the operational characteristics of the parts of the steam generator feedwater inlet horizontal pipe, thermal stratification takes place particularly frequently. However, the thermal stress due to thermal stratification at the steam generator feedwater inlet horizontal pipe was not reflected in the design stage of old plants(Kori Unit No.1, 2, 3 and 4, Yeonggwang Unit No. 1 and 2, and Uljin Unit No. 1 and 2; referred to as old-style power plants hereinafter). Accordingly, a verification experiment was performed for thermal stratification in the horizontal inlet nozzle steam generator of old-style plants. If thermal stratification occurred in the horizontal pipe of an old-style power plant, numerical analysis of the temperature distribution of the pipes and fluids was conducted. The temperature distributions were compared at the curved part of the pipe and the horizontal pipe before and after the installation of the improved thermal sleeves designed to alleviate thermal stress due to thermal stratification. The thermal stress reduction measure was proven effective at the steam generator inlet horizontal pipe and the curved part of the pipe.
Keywords
S/G Inlet Nozzle; Thermal Stratification; Thermal Sleeve; Gap Effect;
Citations & Related Records
Times Cited By KSCI : 1  (Citation Analysis)
Times Cited By Web Of Science : 0  (Related Records In Web of Science)
Times Cited By SCOPUS : 0
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1 United States Nuclear Regulatory Commission, Bulletin No. 79-13, Revision 1, “Cracking in Feedwater System Piping”, Aug. 30, 1979
2 United States Nuclear Regulatory Commission, Bulletin No. 88-08, June 22, 1988 “Thermal Stresses in Piping Connected to Reactor Coolant Systems”
3 R. Magee, et. al., “J. M. Farley Unit 2 Engineering Evaluation of the Weld Joint Crack in the 6, April. 1988, “SI/RHR piping,” WCAP-11789
4 United States Nuclear Regulatory Commission, Bulletin No. 88-08, Supplement 2, Aug. 4, 1988 “Thermal Stresses in Piping Connected to Reactor Coolant Systems”
5 KINS, KINS/Ar-267, 1994, “Numerical analysis of thermal stratification inside the horizontal pipe(I)”
6 Design Report No. Cenc-1940 Revision 01(Z-160-RA-C01-01), 1986, “Design Report For YONG-GWANG Nuclear Power Plant Units 3 And 4 Steam Generators”
7 P&ID Safety Injection/Shutdown Cooling System, 9-441-N105-001~004
8 United States Nuclear Regulatory Commission, Bulletin No. 79-13, June 25, 1979, “Cracking in Feedwater System Piping”
9 United States Nuclear Regulatory Commission, Bulletin No. 79-13, Revision 2, Oct. 16, 1979, “Cracking in Feedwater System Piping”
10 United States Nuclear Regulatory Commission, Bulletin No. 88-11, Dec. 20, 1988, “Pressurizer Surge Line Thermal Stratification”
11 United States Nuclear Regulatory Commission, Bulletin No. 88-08, Supplement 3, April 11, 1989 “Thermal Stresses in Piping Connected to Reactor Coolant Systems”
12 Westinghouse General Order HK 10600-AR6-AR5, April. 1980, “Korea Electric Company Ko-Ri Unit No. 2”
13 EPRI, “Thermal Stratification, Cycling and Striping (TASCS)”, TR-103581, 1994
14 Kim C.H, Youn B.S, Kim S.N, Yeom H.K. April. 2007, “Experiments on Thermal Stratification in Inlet Nozzle of Steam Generator”, KSME, Vol. 21, No. 4. p654~p663   DOI   ScienceOn
15 Safety Injection/Shutdown Cooling System PSDS, 9-441-N407-001
16 P&ID Reactor Coolant System, 9-431-N105-001006.