Dynamic characteristics of reactor core for pipe break and seismic excitations
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This paper investigates the dynamic responses of the reactor core for main steam line and economizer feedwater line breaks. The tributary pipe breaks in lieu of main coolant loop breaks are considered because leak-before-break evaluation has provided a technical basis for the elimination of double ended guillotine breaks. This paper also calculates the response of the reactor core due to the motions induced from safe shutdown earthquake and operating basis earthquake. The dynamic responses such as fuel assembly shear force, bending moment and displacement, and spacer grid impact loads are carefully investigated. Also, reported in this paper are the different response characteristics of each pipe break and seismic excitation.
Key WordsPipe Break Safe Shutdown Earthquake(SSE) Operating Basis Earthquake(OBE) Fuel Assembly Spacer Grid
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- ASME, 1989, “Rules for Construction of Nuclear Power Components.” Division 1. Subsection NG, Core Support Structures, ASME Boiler and Pressure Vessel Code, Sec. III.Google Scholar
- Gabrielson, V.K., 1966, “SHOCK-A Computer Code for Solving Lumped-Mass Dynamic Systems,” SCL-DR-65-34, Sandia Laboratories, Livermore.Google Scholar
- Jhung, M. J. et al., 1991, “Dynamic Analysis of Reactor Internals for the Tributary Pipe Breaks,” SMiRT 11, Paper J02/3, Tokyo.Google Scholar
- Stokes, F. E. and King, R. A., 1978, “PWR Fuel Assembly Dynamic Characteristics,” BNES, Vibration in Nuclear Plants, Keswick, UK.Google Scholar
- USNRC, 1978, “Methodology for Combining Dynamic Responses,” NUREG-0484.Google Scholar
- USNRC, 1978, “Evaluation of Potential for Pipe Breaks,” NUREG-1061, Vol. 3.Google Scholar