Safety-oriented CFD analysis of the PeLUIt-40 pebble-bed HTGR under partial flow and LOCA scenarios

In this study, the thermal–hydraulic behavior of the Indonesian Micro Reactor PeLUIt-40, a 40 MWt modular pebble-bed high-temperature gas-cooled reactor (HTGR), was analyzed under reduced coolant flow and loss-of-coolant accident (LOCA) conditions. Three-dimensional computational fluid dynamics (CFD) simulations using a porous-media core model and volumetric heat sources from neutronic analysis were performed. Steady-state simulations were conducted for helium flow rates from 100% to 25% of nominal, and a transient LOCA was simulated by reducing flow to zero over ten seconds. The results show that maximum core temperatures increased nonlinearly with reduced flow, exceeding TRISO fuel limits at 25% flow, while outlet duct temperatures remained well homogenized. During the LOCA, passive buoyancy-driven circulation limited temperature rise, stabilizing around 1026 °C. These findings provide preliminary insight into PeLUIt-40 thermal hydraulics, highlighting the need for further validation and extended transient analysis to confirm safety margins.

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Publication Details

Journal
Nuclear Energy and Technology
Published
2026-03-09
DOI
https://doi.org/10.3897/nucet.12.173615
Primary Topic
Nuclear reactor physics and engineering
Type
article
Field-Weighted Citation Impact
0.00

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article

Safety-oriented CFD analysis of the PeLUIt-40 pebble-bed HTGR under partial flow and LOCA scenarios

Farisy Yogatama Sulistyo, Muhammad Thowil Afif, Dmitriy G. Veretennikov
Nuclear Energy and Technology
Nuclear reactor physics and engineering
article

Safety-oriented CFD analysis of the PeLUIt-40 pebble-bed HTGR under partial flow and LOCA scenarios

Farisy Yogatama Sulistyo, Muhammad Thowil Afif, Dmitriy G. Veretennikov
article en

Abstract

In this study, the thermal–hydraulic behavior of the Indonesian Micro Reactor PeLUIt-40, a 40 MWt modular pebble-bed high-temperature gas-cooled reactor (HTGR), was analyzed under reduced coolant flow and loss-of-coolant accident (LOCA) conditions. Three-dimensional computational fluid dynamics (CFD) simulations using a porous-media core model and volumetric heat sources from neutronic analysis were performed. Steady-state simulations were conducted for helium flow rates from 100% to 25% of nominal, and a transient LOCA was simulated by reducing flow to zero over ten seconds. The results show that maximum core temperatures increased nonlinearly with reduced flow, exceeding TRISO fuel limits at 25% flow, while outlet duct temperatures remained well homogenized. During the LOCA, passive buoyancy-driven circulation limited temperature rise, stabilizing around 1026 °C. These findings provide preliminary insight into PeLUIt-40 thermal hydraulics, highlighting the need for further validation and extended transient analysis to confirm safety margins.

Nuclear Energy and TechnologyVol. 12(1)
National Research Tomsk State University (RU), Tomsk Polytechnic University (RU), National Nuclear Energy Agency of Indonesia (ID)
Badan Riset dan Inovasi Nasional
Openalex Percentile: Top 30%
Nuclear reactor physics and engineering
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