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Development of an advanced PWR fuel for OPR1000s in Korea
Authors:Kyu-Tae Kim  Jung-Min Suh
Affiliation:aKorea Nuclear Fuel, Technology and Engineering Division, 1047 Daedukdaero, Dukjin-dong, Yuseong-gu, Daejeon, Republic of Korea
Abstract:The advanced PWR fuel for the OPR1000s in Korea, PLUS7, has been developed to enhance thermal performance, high burnup capability and fuel reliability against grid-to-rod fretting wear and debris. The outstanding design features of PLUS7 include mixing vane mid-grids for increasing thermal performance and minimizing vibration-induced fretting wear, optimized fuel dimensions and advanced zirconium alloys for high burnup capability of 72,000 MWD/MTU, and an optimized fuel rod diameter for reducing pressure drop and improving neutron economy. The fuel assembly and its components performances have been verified through a wide spectrum of mechanical, thermal hydraulic, vibration and fretting wear tests. Based on the verification test results and the evaluations with the help of the KNF design code system, it is found that the PLUS7 fuel will maintain its integrity up to the envisaged burnup of 72,000 MWD/MTU. In addition, the PLUS7 fuel performances were evaluated to be considerably improved in comparison with the current fuel used in the OPR1000s.
Keywords:PWR  pressurized water reactor  PHWR  pressurized heavy water reactor  LWR  light water reactor  OPR1000  optimized power reactor 1000 MWe  KNF  Korea Nuclear Fuel  SG  spacer grid  FA  fuel assembly  FR  fuel rod  GT  guide thimble tube  LTA  lead test assembly
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