18th International Conference on Structural Mechanics in Reactor Technology (SMiRT 18) Beijing, China, August 7-12, 2005 SMiRT18-F05-6 REVIEW OF STRESS ANALYSIS RESULTS ACCORDING TO DECOUPLING CRITERIA CHANGE AND SUGGESTION OF ALTERNATIVE SOLUTION Joong-Kyo Shin * Kyoung-Mo Yang Korea Power Engineering Company, inc. Korea Power Engineering Company, inc. 360-9 Mabuk-ri, Guseong-eup, Yongin-si, 360-9 Mabuk-ri, Guseong-eup, Yongin-si, Gyeonggi-do, 449-713, Korea Gyeonggi-do, 449-713, Korea Phone: 82-31-289-3737, Phone: 82-31-289-3636, Fax: 82-31-289-4109 Fax: 82-31-289-4105 E-mail:
[email protected] E-mail:
[email protected] ABSTRACT For OPR 1000(Optimized Power Reactor 1000) which was called as KSNP(Korean Standard Nuclear Plant), if moment-of-inertia ratio of run to branch pipe (Ir/Ib) is larger than 7 to 1, or diameter ratio of the run to the branch pipe (Dr/Db) is larger than 3 to 1, the branch pipe could be decoupled from the run pipe in piping stress analyses. But, EPRI URD and WRC Bulletin 300 criteria, Ir/Ib ≥ 25, are more difficult to accommodate the design sequence and designers’ convenience, than Ir/Ib ≥ 7. If the branch pipe, branching off the run pipe, cannot be decoupled in a piping stress analysis according to the criterion, Ir/Ib ≥ 25, the design sequence of the branch pipe should be parallel with that of the run pipe. However, in general, the design process for run pipe always precedes the process for the branch pipe, because the works for run pipe closely interfaces with other works such as calculation of penetration loads and size of embedded plate for the pipe support design.