Evaluation of structure integrity of the lifting handle of CRB

Since visual inspection was applied to inspect the control rod blades (CRBs) of nuclear power plants in Taiwan, indications have been found in areas such as roller-pin hole, sheath and tie-rod of CRB. Many preliminary safety analyses with conservative assumptions have been conducted to endorse the continuing operation of the units. The objective of this study is to evaluate the structural integrity of those CRBs during lifting operation. Detailed finite element models of the lifting handle of the CRB are built with emphasis on the postulated crack near the roller-pin hole. Both the D-215 type CRB and the Marathon type CRB are evaluated. It is concluded that the structural integrity is guaranteed even under the worst postulated situation.