The safety-by-design™ approach adopted for the design of the International Reactor Innovative and Secure (IRIS) resulted in the elimination by design of some of the main accident scenarios classically applicable to Pressurized Water Reactors (PWR) and to the reduction of either consequences or frequency of the remaining classical at-power accident initiators. As a result of such strategy the Core Damage Frequency (CDF) from at-power internal initiating events was reduced to the 10−8/ry order of magnitude, thus elevating CDF from external events (seismic above all) to an even more significant contributor than what currently experienced in the existing PWR fleet. The same safety-by-design™ approach was then exported from the design of the IRIS reactor and of its safety systems to the design of the IRIS Nuclear Steam Supply System (NSSS) building, with the goal of reducing the impact of seismically induced scenarios. The small footprint of the IRIS NSSS building, which includes all Engineered Safety Features (ESF), all the emergency heat sink and all the required support systems makes the idea of seismic isolation of the entire nuclear island a relatively easy and economically competitive solution. The seismically isolated IRIS NSSS building dramatically reduces the seismic excitation perceived by the reactor vessel, the containment structure and all the main IRIS ESF components, thus virtually eliminating the seismic-induced CDF. This solution is also contributing to the standardization of the IRIS plant, with a single design compatible with a variety of sites covering a wide spectrum of seismic conditions. The conceptual IRIS seismic isolation system is herein presented, along with a selection of the preliminary seismic analyses confirming the drastic reduction of the seismic excitation to the IRIS NSSS building. Along with the adoption of the seismic isolation system, a more refined approach to the computation of the fragility analysis of the components is also being developed, in order to reduce the undue conservatism historically affecting seismic analysis. The new fragility analysis methodology will be particularly focused on the analysis of the isolators themselves, which will now be the limiting components in the evaluation of the overall seismic induced CDF.
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ASME 2009 Pressure Vessels and Piping Conference
July 26–30, 2009
Prague, Czech Republic
Conference Sponsors:
- Pressure Vessels and Piping
ISBN:
978-0-7918-4371-0
PROCEEDINGS PAPER
Seismic Isolation of the IRIS Nuclear Plant
Alessandro Poggianti,
Alessandro Poggianti
ENEA, Bologna, Italy
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Giuseppe Forasassi,
Giuseppe Forasassi
University of Pisa, Pisa, Italy
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Rosa Lo Frano,
Rosa Lo Frano
University of Pisa, Pisa, Italy
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Giovanni Pugliese,
Giovanni Pugliese
University of Pisa, Pisa, Italy
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Federico Perotti,
Federico Perotti
Politecnico di Milano, Milano, Italy
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Leone Corradi dell’Acqua,
Leone Corradi dell’Acqua
Politecnico di Milano, Milano, Italy
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Marco Domaneschi,
Marco Domaneschi
Politecnico di Milano, Milano, Italy
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Mario D. Carelli,
Mario D. Carelli
Westinghouse Electric Company, Pittsburgh, PA
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Mostafa A. Ahmed,
Mostafa A. Ahmed
Westinghouse Electric Company, Pittsburgh, PA
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Andrea Maioli
Andrea Maioli
Westinghouse Electric Company, Pittsburgh, PA
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Massimo Forni
ENEA, Bologna, Italy
Alessandro Poggianti
ENEA, Bologna, Italy
Fosco Bianchi
ENEA, Bologna, Italy
Giuseppe Forasassi
University of Pisa, Pisa, Italy
Rosa Lo Frano
University of Pisa, Pisa, Italy
Giovanni Pugliese
University of Pisa, Pisa, Italy
Federico Perotti
Politecnico di Milano, Milano, Italy
Leone Corradi dell’Acqua
Politecnico di Milano, Milano, Italy
Marco Domaneschi
Politecnico di Milano, Milano, Italy
Mario D. Carelli
Westinghouse Electric Company, Pittsburgh, PA
Mostafa A. Ahmed
Westinghouse Electric Company, Pittsburgh, PA
Andrea Maioli
Westinghouse Electric Company, Pittsburgh, PA
Paper No:
PVP2009-78042, pp. 289-296; 8 pages
Published Online:
July 9, 2010
Citation
Forni, M, Poggianti, A, Bianchi, F, Forasassi, G, Lo Frano, R, Pugliese, G, Perotti, F, Corradi dell’Acqua, L, Domaneschi, M, Carelli, MD, Ahmed, MA, & Maioli, A. "Seismic Isolation of the IRIS Nuclear Plant." Proceedings of the ASME 2009 Pressure Vessels and Piping Conference. Volume 8: Seismic Engineering. Prague, Czech Republic. July 26–30, 2009. pp. 289-296. ASME. https://doi.org/10.1115/PVP2009-78042
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