In the case of recirculation loops, both the existing and a proposed replacement system were studied. The probability of pipe failure in three major coolant pipings was assessed: the recirculation loops, the primary steam lines, and the main feedwater lines. The Brunswick Steam Electric Plant more ยป at Southport, North Carolina was selected as the pilot plant for the BWR evaluation. Following the study of PWR plants, a study of BWR reactor coolant piping was performed. The study includes both the PWR (Pressurized Water Reactor) and the BWR (Boiling Water Reactor) plants in the United States. The US Nuclear Regulatory Commission (NRC) contracted with the Lawrence Livermore National Laboratory (LLNL) to conduct a study to determine if the probability of occurrence of a double-ended guillotine break (DEGB) in the major coolant piping systems of nuclear power plants is large enough to warrant the current stringent design requirements of designing against the postulated effects of a DEGB. The influence of such residual loads on the LBB margins is discussed in details and typical results are presented.
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