Abstract
The Advanced Boiling Water Reactor (ABWR) design is based on construction and operating experience of nuclear power plants in Japan, United States, and Europe. To optimize the plant arrangement of the Advanced Boiling Water Reactor (ABWR) and to verify the structural feasibility to carry design loads a study was conducted. To arrive at an optimized plant arrangement with a minimum size reactor building (RB), a circular cylindrical reinforced concrete containment vessel (RCCV) with a flat top slab and a monolithically connected diaphragm slab has been selected. The Simplified Boiling Water Reactor (SBWR) is being developed as a standardized 600 MWe Advanced Light Water Reactor. The design concept of the SBWR is based on simplicity and passive features to enhance safety and reliability, improve performance and increase economic viability. Due to the use of passive containment cooling, SBWR has features that are different from those of existing designs. The objectives of the study for the ABWR containment and RB are to perform a structural analysis of the containment and RB and to evaluate the structure for conformance to the U.S. NRC requirements. The main objective of the studies for the SBWR is to demonstrate the structural design feasibility of the containment for the pressure and the temperature response associated with the passive systems adopted for the SBWR.
Sign-in/Register to access full text options 
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a callDisclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.
