Ring Model Development and Validation for Prismatic HTGR Core Thermal-hydraulics and Safety Analysis

Hua, T.Q.; Ooi, Zhiee Jhia; Hu, Rui; Zou, Ling

doi:10.2172/1825484

Cited by 6 publications

(7 citation statements)

References 5 publications

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“…is negligible [24]. This is only true under steady-state and some transient conditions, so the unit cell model fails the acid test for most transients.…”

Section: Review Of Existing Approaches -Neams and Beyondmentioning

confidence: 97%

Improvements in High Temperature Gas Cooled Reactor Modeling Capabilities in the Pronghorn Code

Schunert,

Mohammad Jaradat,

Calvin

et al. 2022

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“…is negligible [24]. This is only true under steady-state and some transient conditions, so the unit cell model fails the acid test for most transients.…”

Section: Review Of Existing Approaches -Neams and Beyondmentioning

confidence: 97%

Improvements in High Temperature Gas Cooled Reactor Modeling Capabilities in the Pronghorn Code

Schunert,

Mohammad Jaradat,

Calvin

et al. 2022

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“…This domain size makes a PCC computationally costly to model unless efforts are made to reduce the domain size. For example, Hua et al [15] implemented the ring model approach proposed by Strydom et al [16] to analyze a PCC scenario in the High Temperature Test Facility (HTTF). The horizontal orientation of the HC-HTGR makes the assumption of azimuthal symmetry used to develop the ring model invalid due to several factors.…”

Section: D Core Conduction Modelmentioning

confidence: 99%

Semi-Annual Report for Horizontal Compact High Temperature Gas Reactor (HC-HTGR) Development during Performance Period October 2022-March 2023

Jeong¹,

Hollrah²,

Lisowski³

et al. 2023

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“…Other components and regions in the RPV are modeled by concentrical rings in a similar approach adopted by the ring model [6]. Solid components are transformed into concentrical rings with conserved material properties and cross-sectional areas.…”

Section: Sam Modeling Of the Whole Systemmentioning

confidence: 99%

“…Potential improvements exist for adopting more precise transformation rather than the approximation of Eqn. (6). The right plot in Figure 7 compares the 2D local axial-lateral temperature distribution along the pitch between the fuel and coolant.…”

Section: Validation Of Steady-state Predictionmentioning

confidence: 99%

“…The System Analysis Module (SAM) is a modern simulation tool being actively developed at Argonne National Laboratory to support the system-level analysis of advanced non-water reactors including HTGRs [5]. Previous development and validation efforts have demonstrated that a "2-D ring model" with reasonable performance can be implemented in SAM for prismatic HTGR cores [6]. In the ring model, components such as fuel pins, moderator blocks, reflectors, and coolant channels are all lumped into concentrical rings forming a multi-layer cylindrical core highlighting the core-wise thermal conduction paramount in long-term transients.…”

Section: Introductionmentioning

confidence: 99%

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Representative-cell-based Modeling of HTTF in SAM

Zhang

Hua

Ooi

et al. 2022

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Although the current nuclear power market is primarily occupied by the light water reactors (LWRs), the TRISO-fueled helium-cooled graphite-moderated high temperature gas reactors (HTGRs) are drawing growing attention as the nuclear power industry marches towards more advanced systems. Compared to that of conventional LWRs, the thermal hydraulics of HTGR cores show extra complexity from their multi-scale heat transfer mechanisms with varying importance during different operation modes or transient stages. The modeling of HTGR cores for the system analysis purpose therefore faces the challenge of reaching reasonable fidelity and accuracy while maintaining sufficient simplicity. Previous development and validation efforts have demonstrated that a "2-D ring model" with reasonable performance can be implemented in the System Analysis Module (SAM) for prismatic HTGR cores. In the current project, an alternative modeling methodology based on "representative cells" is proposed for the typical prismatic core of HTGRs. Different from the previous ring model approach, the proposed methodology first separately models and then combines the small-and large-scale thermal conductions, by connecting representative local heat transfer units (cells) with effective corewise thermal resistance. A modeling practice for an integral high-temperature test facility (HTTF) elaborates the modeling details. Steady-state validation of the resultant candidate model is performed against a higher-resolution benchmark from a 3D-1D coupled simulation, which shows satisfactory prediction with reasonably captured global parameters and well-represented temperature fields. A postulated pressurized conduction cooldown (PCC) is also simulated and analyzed, demonstrating the model's capability of transient prediction with physically captured phenomena resolved in both small and large temporal and spatial scales. In general, the current work achieves a preliminary success in proposing a methodology using representative cells to model prismatic HTGR cores in SAM. Future efforts are envisioned with more validation activities and with potential modeling improvements to eventually achieve the high confidence on a high-fidelity robust modeling methodology with reasonable accuracy.

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Ring Model Development and Validation for Prismatic HTGR Core Thermal-hydraulics and Safety Analysis

Cited by 6 publications

References 5 publications

Improvements in High Temperature Gas Cooled Reactor Modeling Capabilities in the Pronghorn Code

Improvements in High Temperature Gas Cooled Reactor Modeling Capabilities in the Pronghorn Code

Semi-Annual Report for Horizontal Compact High Temperature Gas Reactor (HC-HTGR) Development during Performance Period October 2022-March 2023

Representative-cell-based Modeling of HTTF in SAM

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