Fundamental study on design margin for fast reactor plant with seismic isolation system

A sodium-cooled fast reactor plant uses liquid metal sodium as a coolant. Sodium has a high boiling point and excellent heat transfer capabilities. These properties allow the reactor to operate at low pressure. However, thermal fatigue occurs due to repeated thermal expansion and contraction within the creep temperature range. Accordingly, the fast reactor’s components and piping are designed with thin walls. Seismic isolation systems are used to reduce the seismic loads acting on components. Seismic isolation systems are used to reduce the seismic loads acting on components. Research and development of seismic design methods is progressing. Applying seismic isolation to nuclear power plants requires clarifying the design margin approach for equipment in fast reactor plants and seismic isolation devices. Here, the design margin refers to the margin relative to the design criteria for components or seismic isolation systems, i.e. the ratio of seismic response to the design criteria for the design basis ground motion, The design margin should be set to a value equal to or greater than the safety margin. Here, the safety margin is defined as the minimum margin specified in regulatory requirements and standards. This report proposes an approach for determining design margins for fast reactor plants with the horizontal seismic isolation system. We conducted the seismic response analysis of the reactor building and created the fragility curve with buckling evaluation of the reactor vessel. Based on these results, an approach for determining design margins of the components and the horizontal seismic isolation system was investigated.

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Publication Details

Journal
Journal of Nuclear Science and Technology
Published
2026-06-12
DOI
https://doi.org/10.1080/00223131.2026.2680222
Primary Topic
Fluid Dynamics Simulations and Interactions
Type
article
Field-Weighted Citation Impact
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article

Fundamental study on design margin for fast reactor plant with seismic isolation system

Masaki Yukawa, Shigeki OKAMURA, T. Hirayama, Akira Yamaguchi et al.
Journal of Nuclear Science and Technology
Fluid Dynamics Simulations and Interactions
article

Fundamental study on design margin for fast reactor plant with seismic isolation system

Masaki Yukawa, Shigeki OKAMURA, T. Hirayama, Akira Yamaguchi, Shotaro Watanabe, Satoshi Fujita, Risako Nakashima
article en

Abstract

A sodium-cooled fast reactor plant uses liquid metal sodium as a coolant. Sodium has a high boiling point and excellent heat transfer capabilities. These properties allow the reactor to operate at low pressure. However, thermal fatigue occurs due to repeated thermal expansion and contraction within the creep temperature range. Accordingly, the fast reactor’s components and piping are designed with thin walls. Seismic isolation systems are used to reduce the seismic loads acting on components. Seismic isolation systems are used to reduce the seismic loads acting on components. Research and development of seismic design methods is progressing. Applying seismic isolation to nuclear power plants requires clarifying the design margin approach for equipment in fast reactor plants and seismic isolation devices. Here, the design margin refers to the margin relative to the design criteria for components or seismic isolation systems, i.e. the ratio of seismic response to the design criteria for the design basis ground motion, The design margin should be set to a value equal to or greater than the safety margin. Here, the safety margin is defined as the minimum margin specified in regulatory requirements and standards. This report proposes an approach for determining design margins for fast reactor plants with the horizontal seismic isolation system. We conducted the seismic response analysis of the reactor building and created the fragility curve with buckling evaluation of the reactor vessel. Based on these results, an approach for determining design margins of the components and the horizontal seismic isolation system was investigated.

Journal of Nuclear Science and Technology
Japan Atomic Energy Agency (JP), Obayashi (Japan) (JP), Mitsubishi Group (Japan) (JP), Tokyo Denki University (JP), Nuclear Waste Management Organization (CA)
Openalex Percentile: Top 6%
Fluid Dynamics Simulations and Interactions
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