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Pressure Wave Propagation in the Discharge Piping with Water Pool  

Bang Young S. (Korea Institute of Nuclear Safety)
Seul Kwang W. (Korea Institute of Nuclear Safety)
Kim In-Goo (Korea Institute of Nuclear Safety)
Publication Information
Nuclear Engineering and Technology / v.36, no.4, 2004 , pp. 285-294 More about this Journal
Abstract
Pressure wave propagation in the discharge piping with a sparger submerged in a water pool, following the opening of a safety relief valve, is analyzed. To predict the pressure transient behavior, a RELAP5/MOD3 code is used. The applicability of the RELAP5 code and the adequacy of the present modeling scheme are confirmed by simulating the applicable experiment on a water hammer with voiding. As a base case, the modeling scheme was used to calculate the wave propagation inside a vertical pipe with sparger holes and submerged within a water pool. In addition, the effects on wave propagation of geometric factors, such as the loss coefficient, the pipe configuration, and the subdivision of sparger pipe, are investigated. The effects of inflow conditions, such as water slug inflow and the slow opening of a safety relief valve are also examined.
Keywords
pressure wave; propagation; reflection wave; RELAP5/MOD3; water hammer experiment;
Citations & Related Records
Times Cited By KSCI : 1  (Citation Analysis)
연도 인용수 순위
1 G.V.Aronovich, et al., Water Hammer and Surge Tanks, Izdatel' stvo 'Nauka', Moskva (1968)
2 Information System Laboratory Inc., RELAP5/MOD3.3 Code Manual, Rockville, MD, NUREG/CR-5535 (2002)
3 Stubbe, E.J., Vanhoenacker L., and Otero, R., RELAP5/MOD3 Assessment for Calculation of Safety and Relief Valve Discharge Piping Hydrodynamic Loads, USNRC, NUREG/IA-0094 (1990)
4 G.B.Doh, et al., Evaluation of the Reflooding Behavior of Blowdown and Condensation (B&C) Loop with a Prototype Sparer Using the RELAP5 Code, Paper 3345, Proceedings of ICAPP' 03, Cordoba, Spain, May (2003)
5 B.Mavko, et al., A Sketch of a Facility for Water Hammer Problem, CAMP Activity in Slovenia, Presented at the CAMP Meeting, Washington D.C., October (1996)
6 United States Nuclear Regulatory Commission, Standard Review Plan, USNRC, Washington, D.C., NUREG-0800. (1988)
7 United States Nuclear Regulatory Commission, Final Safety Evaluation Report Related to the Certification of the System 80+ Design, USNRC, Washington, D.C., NUREG-1462, August (1994)
8 Kwang W. Seul, et al., Simulation of Multiple Steam Generator Tube Rupture (SGTR) Event Scenario, Journal of KNS, Vol. 35, No.3, pp 179-190, June (2003)   과학기술학회마을
9 Korea Electric Power Corp., Korean Next Generation Reactor Standard Safety Analysis Report, Seoul (1998)
10 Young S. Bang, et al., Thermal-hydraulic Response in the Discharge Piping with Water Pool, PVP-Vol.435, 2002 ASME Pressure Vessels and Piping Conference, Vancouver, Canada, August (2002)