A shutdown cooling (SDC) system was observed to have pressure spikes that lifted relief valves upon alignment with the Reactor Coolant System (RCS) hot leg. Investigations showed that gas could accumulate at several local high points of the system. An evaluation was conducted with the primary objective of determining if the accumulated gas could lift the relief valve and the secondary objective of increased understanding of how the gas affected the system. Modeling was performed to evaluate the effect of various gas pocket sizes on the over pressurization. Pressure data from operation of the LPSI pumps was used to test the model. This investigation determined that pressure magnitudes produced during the alignment of the SDC system would be limited by the acceleration of the fluid mass for small bubbles and by compressibility of the gas pocket for large bubbles. The study results showed that pressure was maximized for small to medium sized gas bubbles at locations outside of containment.
Skip Nav Destination
ASME 2002 Pressure Vessels and Piping Conference
August 5–9, 2002
Vancouver, BC, Canada
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
0-7918-1946-9
PROCEEDINGS PAPER
Evaluation of Shutdown Cooling Transients Using Simplified Models Available to Purchase
Gregory Zysk
Gregory Zysk
Altran Corporation
Search for other works by this author on:
Gregory Zysk
Altran Corporation
Paper No:
PVP2002-1136, pp. 115-120; 6 pages
Published Online:
August 14, 2008
Citation
Zysk, G. "Evaluation of Shutdown Cooling Transients Using Simplified Models." Proceedings of the ASME 2002 Pressure Vessels and Piping Conference. Thermal Hydraulic Problems, Sloshing Phenomena, and Extreme Loads on Structures. Vancouver, BC, Canada. August 5–9, 2002. pp. 115-120. ASME. https://doi.org/10.1115/PVP2002-1136
Download citation file:
8
Views
Related Proceedings Papers
Related Articles
Fukushima Unit 2 Accident Simulation With MELCOR 2.1
ASME J of Nuclear Rad Sci (April,2018)
Effects of Air Entrainment on the Ability of Air Vessels in the Pressure Surge Suppressions
J. Fluids Eng (September,2000)
Modeling Two-Phase Flow Inside an Electrical Submersible Pump Stage
J. Energy Resour. Technol (December,2011)
Related Chapters
PSA Level 2 — NPP Ringhals 2 (PSAM-0156)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Modeling of SAMG Operator Actions in Level 2 PSA (PSAM-0164)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Subsection NCA—General Requirements for Division 1 and Division 2
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 1, Third Edition