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AbstractAbstract
[en] Damage to the thermal shield support structures of three pressurized water reactors (PWRs) due to flow-induced vibrations was recently discovered during refueling. In two of the reactors, severe damage occurred to the thermal shield, and in one reactor the core support barrel (CSB) was damaged, necessitating extended outages for repairs. In all three reactors, several of the thermal shield supports were either loose, damaged, or missing. The Nuclear Regulatory Commission requested that Oak Ridge National Laboratory analyze ex-core neutron detector noise data to determine the feasibility of detecting incipient thermal shield support degradation. Reactor manufacturers and utilities provided the noise data for the analysis. Finite element model calculations were also performed. Results of the noise data analysis indicate that thermal shield support degradation probably began early in the life of both severely damaged plants. The degradation was characterized by shifts in the resonant frequencies of core internal structures and the appearance of new resonances in the ex-core neutron detector noise
Primary Subject
Source
1986; 35 p; ASME pressure vessel and piping conference and exhibit; Chicago, IL (USA); 20-24 Jul 1986; Available from NTIS, PC A03/MF A01 as TI86013397
Record Type
Report
Literature Type
Conference
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