Development of a Reference Model for Molten-Salt-Cooled Pebble-Bed Reactor Using SAM

Hu, Guojun; O’Grady, Daniel; Zou, Ling; Hu, Rui

doi:10.2172/1674975

Cited by 6 publications

(14 citation statements)

References 9 publications

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“…In this section, the updated porous-medium model will be demonstrated using a more realistic and complex reference PB-FHR model developed from a previous study [13]. The generic PB-FHR model was based on the University of California, Berkeley, Mk1 design [14], but incorporated some design characteristics of a preliminary commercial FHR design because of its higher readiness for licensing application.…”

Section: Pb-fhr Code Demonstrationmentioning

confidence: 99%

“…The generic PB-FHR model was based on the University of California, Berkeley, Mk1 design [14], but incorporated some design characteristics of a preliminary commercial FHR design because of its higher readiness for licensing application. The primary system of the generic PB-FHR model is shown in Figure 17, which is based on the Mk1 SAM model presented in reference [13]. Upon exiting the salt collection ring within the graphite reflector, the hot salt travels upwards, 1, where it exits the reactor vessel.…”

Section: Pb-fhr Code Demonstrationmentioning

confidence: 99%

“…In the previous study, only the steady-state condition was considered for the standalone core model [13]. In this study, to examine how the new multi-scale model improves on the original model, a transient simulation is considered.…”

Section: Standalone Two-dimensional Fhr Core Modelmentioning

confidence: 99%

“…In this subsection, the standalone 2D core model presented in the previous subsection is coupled to a 1D system model for the remaining primary system. The coupling is through boundary interface data exchange, as described in reference [13]. The main purpose of this case is to demonstrate that the newly developed model and code implementation work in a very complex input model that requires the use of MOOSE MultiApp and Picard iteration for coupling and MOOSE restart capability for a robust coupling.…”

Section: Coupled 2d Core and 1d Systemmentioning

confidence: 99%

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Explicit Modeling of Pebble Temperature in the Porous-medium Framework for Pebble-bed Reactors Applications

Zou¹,

O’Grady²,

Hu³

et al. 2021

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In this study, an explicit model for pebble temperature calculations in the framework of a porous-medium approach has been developed and implemented in the SAM code. The solidphase energy conservation equation, including the explicit modeling of pebble temperature, is a multi-scale model, which can predict the macroscopic (pebble-bed) and microscopic (pebble) temperature distributions under both steady-state and transient conditions. Extensive and successful code verifications and demonstrations have been performed for this newly developed model. By explicitly modeling pebble temperatures, this new model addresses a major deficiency of the previously implemented model, which assumed a local solid-phase thermal equilibrium that is not appropriate for pebble-bed reactor design and safety analysis applications.

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Section: Pb-fhr Code Demonstrationmentioning

confidence: 99%

Section: Pb-fhr Code Demonstrationmentioning

confidence: 99%

Section: Standalone Two-dimensional Fhr Core Modelmentioning

confidence: 99%

Section: Coupled 2d Core and 1d Systemmentioning

confidence: 99%

See 2 more Smart Citations

Explicit Modeling of Pebble Temperature in the Porous-medium Framework for Pebble-bed Reactors Applications

Zou¹,

O’Grady²,

Hu³

et al. 2021

Self Cite

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“…In FY2020, a generic model was developed to demonstrate the ability of SAM to simulate the primary loop of a pebble-bed fluoride-salt-cooled, high temperature reactor (PB-FHR) [18]. The model was designed to be representative of a generic PB-FHR by building on the University of California, Berkeley (UCB) Mk1 design [19] and considering some of the publicly-shared features of early commercial designs.…”

Section: Development Of a Reference Fhr Modelmentioning

confidence: 99%

SAM Code Enhancement, Validation, and Reference Model Development for Fluoride-salt-cooled High-temperature Reactors

O’Grady¹,

Mui²,

Lee³

et al. 2021

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The System Analysis Module (SAM) is under development at Argonne National Laboratory as a modern system-level modeling and simulation tool for advanced non-light water reactor safety analyses. It utilizes the object-oriented application framework MOOSE to leverage the modern software environment and advanced numerical methods. The capabilities of SAM are being extended to enable the transient modeling, analysis, and design of various advanced nuclear reactor systems. This report summarizes recent progress under DOE-NE's Nuclear Energy Advanced Modeling and Simulation program in SAM code development, demonstration, and validation to support transient safety analysis of Fluoride-salt-cooled High-temperature Reactors.The 1-D spherical geometry heat conduction model is implemented in SAM and verified with several verification test cases. The porous medium pressure drop correlations for pebble bed are converted and implemented into the 1-D fluid flow model to support the modeling of 1-D system models with pebble beds. A reference primary loop model of PB-FHR is developed, based on the UC Berkeley Mk1 FHR design and incorporated some design features in Kairos Power's KP-FHR core. A reference standard problem of the reactor primary loop model is foundational to the methodologies employed by NRC to verify the adequacy of computer codes and evaluation models. Additional SAM validation is successfully performed against CIET LOFC experiments. Good agreements between the SAM simulation results and the experimental data are obtained during the entire LOFC transient.

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Analysis of Near-Wall Pebble Bed Thermal Conductivity for Energy Applications

Wada,

Eixenberger,

Stout

et al. 2023

ACS Omega

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Pebble beds have been employed in thermal storage and energy systems, where they are typically used to promote heat exchange in high-temperature environments. Understanding the heat conduction of the entire pebble bed could aid in the material selection of the pebbles themselves and structural components, system design, and safety monitoring. However, the thermal conductivity of pebble beds can change significantly near geometric boundaries. Using a complex multilayer analytical model in conjunction with a line source probe, we found a substantial increase in the thermal conductivity of a sintered bauxite pebble bed in the near-wall region (7.6 W m −1 K −1 ) compared to the bulk (0.59 W m −1 K −1 ). We investigated this difference by comparing porosity results, acquired with micro-CT, of 33.18 and 33.31% at approximately one pebble width surrounding the probe (near-wall) and the bulk of the pebble bed, suggesting that the thermal conductivity is largely altered by thermal contact resistance in the nearwall regime.

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Development of a Reference Model for Molten-Salt-Cooled Pebble-Bed Reactor Using SAM

Abstract: 60439. For information about Argonne and its pioneering science and technology programs, see www.anl.gov.

Cited by 6 publications

References 9 publications

Explicit Modeling of Pebble Temperature in the Porous-medium Framework for Pebble-bed Reactors Applications

Explicit Modeling of Pebble Temperature in the Porous-medium Framework for Pebble-bed Reactors Applications

SAM Code Enhancement, Validation, and Reference Model Development for Fluoride-salt-cooled High-temperature Reactors

Analysis of Near-Wall Pebble Bed Thermal Conductivity for Energy Applications

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