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Thermal-Hydraulic Analysis of a Hypothetical Complete Failure of One Shroud Access Hole in a Boiling Water Reactor

Lih-Yih Liao

Nuclear Technology / Volume 97 / Number 3 / March 1992 / Pages 282-293

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34636

Cracks have been observed in the welds of the shroud support access hole cover plates at Peach Bottom Unit 3 as well as at the Chinshan nuclear power plant. The cracks could potentially result in complete weld failure and, as a consequence, a coreflow bypass. Analysis of the postulated complete weld failure of the Chinshan nuclear power plant shroud support access hole cover plate is performed with RETRAN-02/MOD3. The results show that some confusing phenomena could be observed. The reactor operator should be aware of the phenomena to avoid the likelihood of misoperation. Also, a special procedure needs to be established to deal with this event.