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1983•Am. Soc. Mech. Eng., Pressure Vessels Piping Div., (Tech. Rep.) PVP; (United States)Requires access

Secondary system piping analysis including seismic and a loss of coolant accident

Wei Sun, N. Lee, R. Lee

Open publisher page 1 citations

Abstract

A general analysis approach which includes the dynamic time-history analysis and the static analysis is presented. The secondary system piping is that piping which excludes the primary coolant loop in the Pressurized Water Reactor (PWR) plant, and the main steam, feedwater and reactor recirculation piping in the Boiling Water Reactor (BWR) plant. Piping response to the induced motion from a Loss of Coolant Accident (LOCA) such as stress, displacement, acceleration, support loads and penetration loads are carefully investigated and the system is designed to guarantee the safe shut down of nuclear plants during LOCA and seismic events.

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What this paper is about

A general analysis approach which includes the dynamic time-history analysis and the static analysis is presented. The secondary system piping is that piping which excludes the primary coolant loop in the Pressurized Water Reactor (PWR) plant, and the main steam, feedwater and reactor recirculation piping in the Boiling Water Reactor (BWR) plant. Piping response to the induced motion from a Loss of Coolant Accident (LOCA) such as stress, displacement, acceleration, support loads and penetration loads are carefully investigated and the system is designed to guarantee the safe shut down of nuclear plants during LOCA and seismic events.

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Available abstract

A general analysis approach which includes the dynamic time-history analysis and the static analysis is presented. The secondary system piping is that piping which excludes the primary coolant loop in the Pressurized Water Reactor (PWR) plant, and the main steam, feedwater and reactor recirculation piping in the Boiling Water Reactor (BWR) plant. Piping response to the induced motion from a Loss of Coolant Accident (LOCA) such as stress, displacement, acceleration, support loads and penetration loads are carefully investigated and the system is designed to guarantee the safe shut down of nuclear plants during LOCA and seismic events.

Key concepts: Piping, Boiler feedwater, Coolant, Pressurized water reactor, Loss-of-coolant accident, Nuclear engineering, Boiling, Shutdown

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