COMPUTATION FLUID DYNAMICS ANALYSIS FOR GENERIC SMALL MODULAR REACTOR CONTAINMENT SEPARATE EFFECTS TEST

Hendrickson, Grant [Oregon State University]; Wu, Qiao [Oregon State University]; Fossum, Kenneth Lee [Idaho National Laboratory] (ORCID:0000000256632125); Bhowmik, Palash Kumar [Idaho National Laboratory] (ORCID:0000000335717805)

DOE OSTI · 3362747

COMPUTATION FLUID DYNAMICS ANALYSIS FOR GENERIC SMALL MODULAR REACTOR CONTAINMENT SEPARATE EFFECTS TEST

Hendrickson, Grant [Oregon State University]·Wu, Qiao [Oregon State University]·Fossum, Kenneth Lee [Idaho National Laboratory] (ORCID:0000000256632125)·Bhowmik, Palash Kumar [Idaho National Laboratory] (ORCID:0000000335717805)

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Abstract

It is desirable for fourth-generation Small Modular Reactors to be passively cooled in standard and accident operations. Passive Containment Cooling Systems can reject heat from the containment structure, without using pumps or blowers. The targeted design containment structure is a large, domed, stainless steel, cylindrical vessel. In a postulated Design Basis Accident, steam will flash inside containment. Steam condensation occurs on the inner containment wall and transfers heat through the steel containment into a large body of water known as the annular reservoir (AR) surrounding the vessel serving as the ultimate heat sink. Natural circulation drives the flow in the AR and heat will be released to the environment by evaporation of water. Unique containment geometry requires a separate effects test (SET) facility for the verification and validation of the computer code and evaluation model development and assessment for reactor licensing efforts. In this study, STAR-CCM+, a computational fluid dynamics (CFD) code was used to inform the decision-making process on the design of the SET. The CFD simulation modeled, a two-phase turbulent flow with fluid film development and heat transfer for different containment geometries. The Reactor Excursion and Leak Analysis Program will also be used in a code-to-code verification against the CFD results.

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21 - SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS 22 - GENERAL STUDIES OF NUCLEAR REACTORS 42 - ENGINEERING 97 - MATHEMATICS AND COMPUTING 99 - GENERAL AND MISCELLANEOUS Computational Fluid Dynamics Fluid Film Nuclear Reactor Thermal Hydraulics Passive Containment Cooling System Separate Effects Test

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Hendrickson, Grant [Oregon State University], Wu, Qiao [Oregon State University], Fossum, Kenneth Lee [Idaho National Laboratory] (ORCID:0000000256632125), Bhowmik, Palash Kumar [Idaho National Laboratory] (ORCID:0000000335717805). 2025-03-09. COMPUTATION FLUID DYNAMICS ANALYSIS FOR GENERIC SMALL MODULAR REACTOR CONTAINMENT SEPARATE EFFECTS TEST. https://www.osti.gov/biblio/3362747

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