[3K01-06] Seismic Technologies, Development of SMR

[3K06] Technical Demonstration for NuScale “VOYGR^TM”

(4) Preliminary Physical Damage Evaluation of Reactor Building for Aircraft Impact Assessment

*Yuki Sato¹, Shunji Kataoka¹, Eiji Kawada¹, Yasutomi Morimoto¹, Tomoyuki Umezawa¹, Takahisa Kawase², Daisuke Koike³, Paul Boyadjan⁴ (1. JGC, 2. Kajima, 3. IHI, 4. NuScale Power)

Keywords:SMR, NuScale, VOYGR, AIA, Reactor Building

NuScale SMR Nuclear Power Plant (hereinafter called VOYGR^TM) in the United States adopts Reinforced Concrete (RC) structures in the design certificate phase. However, currently, new building structures using Steel-concrete Composite (SC) structures have been studied, and the subsequent Aircraft Impact Assessment (AIA) has been conducted in accordance with US regulations. In case of assuming the introduction of VOYGR^TM to Japan, the AIA following Japanese regulations is required as well. As a preliminary approach, this paper provides study results for building protections against assumptive aircraft impact loads using the simplified reactor building analysis model.