The paper presents study result on an innovative, intelligent and inexpensive BWR (iBR). It is the first Generation III.7 reactor after the Fukushima Daiichi accident. It has incorporated lessons learned from the Fukushima Daiichi accident and WENRA safety objectives. It has innovative safety to cope with devastating natural disasters including a giant earthquake, a large tsunami and a monster hurricane. The iBR can survive passively such devastation and a very prolonged SBO without any support from the outside of a site up to 7 days even preventing core melt. It, however, is based on the well-established proven ABWR design. NSSS is exactly the same as that of the current ABWR. As for safety design it has a double cylinder RCCV (Mark W containment) and an in-depth hybrid safety system (IDHS). The Mark W containment has double FP confinement barriers and the in-containment filtered venting system (IFVS) that enable passively no emergency evacuation outside the immediate vicinity of the plant for a SA. It has a large volume to hold hydrogen, a core catcher, a passive flooding system and a passive containment cooling system (PCCS) establishing passively practical elimination of containment failure even in a long term. The IDHS consists of 4 division active safety systems for a DBA, 2 division active safety systems for a SA and built-in passive safety systems (BiPSS) consisting of an isolation condenser (IC) and the PCCS for a SA. IC/PCCS pools have enough capacity for 7 day grace period. The IC/PCCS, core and spent fuel pool are enclosed inside the CV building and protected against a large airplane crash. The iBR can survive a large airplane crash only by the CV building and the built-in passive safety systems therein. The dome of the CV building consists of a single wall made of steel and concrete composite. This single dome structure facilitates a short-term construction period and cost saving. CV diameter is smaller than that of most PWR resulting in the smaller R/B. The iBR is based on the proven ABWR technology and ready for construction. No new technology is incorporated but design concept and philosophy are initiative and innovative.
- Nuclear Engineering Division
The iBR: A Generation III.7 Reactor After the Fukushima Daiichi Accident
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Sato, T, Matsumoto, K, Kurosaki, T, & Maida, M. "The iBR: A Generation III.7 Reactor After the Fukushima Daiichi Accident." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security. Prague, Czech Republic. July 7–11, 2014. V003T05A011. ASME. https://doi.org/10.1115/ICONE22-30309
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