Assessment of Fast Reactor Hot Channel Factor Calculation Capability in Griffin and NekRS

Shemon, Emily; Yu, Yang; Park, Hansol; Brennan, Colin

doi:10.2172/1820633

Cited by 5 publications

(5 citation statements)

References 10 publications

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“…Three new capabilities for modeling LMFR reactors were recently uploaded to the VTB. This included a detailed heterogeneous neutronics model for a lead-cooled fast reactor assembly [8] (shown in Figure 14), an assembly duct bowing benchmark problem that uses openly available MOOSE modules [9] (shown in Figure 15), and new subchannel benchmarks for LMFR lattices [10] (shown in Figure 16).…”

Section: Liquid Metal Fast Reactors (Lmfr)mentioning

confidence: 99%

“…Model development activities at the VTB were previously focused on MSR and FHR concepts. Those were previously identified as key gaps in the modeling and simulation space [8] that were not investigated by other programs. As NRIC engages with potential demonstrators, a new priority list was developed in coordination with the leadership team:…”

Section: Model Development Activitiesmentioning

confidence: 99%

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Overview of Virtual Test Bed FY23 Activities

Abou Jaoude,

Giudicelli,

Walker

et al. 2023

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This milestone report highlights progress achieved within the Virtual Test Bed (VTB) project during Fiscal Year (FY) 2023. The VTB consists of an open-source repository of state-of-the-art simulation examples for advanced reactor types. Its objective is to help accelerate reactor maturation and deployment by providing 'reference' models that can be openly accessed, improved upon, and re-purposed for proprietary applications. The main accomplishments are summarized below:1. Models on the repository were consistently maintained and new improvements were developed to improve the useability of the website. These new improvements include a tagging system and testing of computationally expensive models.

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Section: Liquid Metal Fast Reactors (Lmfr)mentioning

confidence: 99%

Section: Model Development Activitiesmentioning

confidence: 99%

Overview of Virtual Test Bed FY23 Activities

Abou Jaoude,

Giudicelli,

Walker

et al. 2023

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“…Presently, there is no capability in Griffin to re-homogenize materials by adjusting the sodium quantity within a block to match the available volume fraction, which is what is needed to model backfill in a fully homogenous or duct-heterogeneous approach. Additionally, a fully heterogeneous approach for a deformed SFR core hasn't been documented by the Griffin team although a fully heterogenous lead cooled fast reactor assembly has been demonstrated and documented on the VTB [18] and [19].…”

Section: Neutronics Considerations and Griffin Statusmentioning

confidence: 99%

FY23 Status Report on MOOSE-Based Approaches to Modeling Core Bowing in Fast Reactors

Wozniak,

Yang,

Shemon

et al. 2023

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Under the U.S. Department of Energy Office of Nuclear Energy's Advanced Modeling and Simulation (NEAMS) Program, an integrated multiphysics approach is being developed to model the core bowing phenomena important to liquid metal-cooled fast reactors. Core bowing is an important passive safety mechanism whereby increased power (which leads to temperature and flux gradients) influences the core to bow into less reactive configurations when the restraint system is properly designed. The phenomenon includes a complex interplay of radiation transport, duct temperature calculations involving fluid flow and heat transfer, and thermo-mechanical responses to the induced temperature and flux gradients. Structural material properties are also important to determining inelastic response to longer term flux gradients which cause irradiation creep and swelling. While core bowing provides a strong negative reactivity feedback when the restraint system is designed properly, it also results in additional forces between assemblies which increase the loads required to extricate them during refueling or control rod movement. Therefore, the restraint system must be designed with these tradeoffs in mind.The first stage of the work, which commenced in FY21 and continues through FY23, assesses thermo-mechanical modeling tools for producing core bowing predictions consistent with conventional tools. The Multiphysics Object Oriented Simulation Environment (MOOSE) Tensor Mechanics and Contact Modules are employed. This status report describes work on additional thermo-mechanical benchmark verification problems with increased complexity from the examples demonstrated in FY21 and FY22.Several benchmark verification examples were selected from the IAEA verification and validation report with increased number of ducts and more complex contact interaction behavior. These examples involve a full symmetric sector with restraint rings at multiple load pad locations to simulate a limited free-bow restraint system concept, as well as irradiation induced swelling and creep effects in a sector. In addition, improvements to the contact module sideset assignment were assessed and compared with previous MOOSE results to verify the contact behavior. The MOOSEbased results were compared to IAEA benchmark participants' results. In every case, the MOOSE results agreed with other simulations results for estimating bowing behavior, providing additional verification basis of the tools for this particular physics application. Estimation of contact forces were mostly in agreement, with a few outlier results. A plan was suggested for dealing with the discrepancies with estimating contact force values.In addition, a 1-way coupling demonstration was performed using subchannel analysis code Pronghorn-SC and MOOSE on an ABR-1000-design sodium-cooled fast reactor assembly to evaluate coolant and duct wall temperatures.

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“…Building upon the success of PROTEUS and Nek5000, work began in FY21 to develop a Multiphysics Object Oriented Simulation Environment (MOOSE)-based [15] capability for more robust and automated coupling. The MOOSE-based Griffin reactor physics code and MOOSEwrapped NekRS thermal fluids codes were individually assessed on a prototypic LFR assembly [16] since they can be coupled via MOOSE's MultiApp System [17] and both can perform highly heterogeneous simulations with few modeling approximations. The LFR design was selected due to the absence of LFR HCFs in the literature, which creates an opportunity for advanced modeling and simulation to fill a critical need.…”

Section: Summary Of Prior Workmentioning

confidence: 99%

“…The cross section library generation procedure was described in detail in last year's report [16]. The MC 2 -3/TWODANT [20] procedure was used to generate 9 energy group cross section sets for materials at different axial zones.…”

Section: Griffinmentioning

confidence: 99%

Progress on Demonstration of a MOOSE-Based Coupled Capability for Hot Channel Factors in Fast Reactors

Park¹,

Yu²,

Shemon³

et al. 2022

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The Laboratory's main facility is outside Chicago, at 9700 South Cass Avenue, Argonne, Illinois 60439. For information about Argonne and its pioneering science and technology programs, see www.anl.gov. DOCUMENT AVAILABILITYOnline Access: U.S. Department of Energy (DOE) reports produced after 1991 and a growing number of pre-1991 documents are available free at OSTI.GOV (http://www.osti.gov/), a service of the US Dept. of Energy's Office of Scientific and Technical Information.

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Assessment of Fast Reactor Hot Channel Factor Calculation Capability in Griffin and NekRS

Cited by 5 publications

References 10 publications

Overview of Virtual Test Bed FY23 Activities

Overview of Virtual Test Bed FY23 Activities

FY23 Status Report on MOOSE-Based Approaches to Modeling Core Bowing in Fast Reactors

Progress on Demonstration of a MOOSE-Based Coupled Capability for Hot Channel Factors in Fast Reactors

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