Prismatic Block Graphite Bypass Test Facility

In a prismatic block core High Temperature Gas-Cooled Reactor (HTGR), a fraction of the core coolant flow (bypass flow) moves through the core via the interstitial and non-cooling passages between the graphite blocks or through the reflector regions (center & side). The bypass flow has been estimated to vary from ~10 to 25% of the total core flow rate.

An experimental and computational investigation has been conducted to study the flow bypass in this type of reactor design. 

 

Test Section Overview

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 Facility Overview

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 CFD Simulation: Gap Crossflow

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