Application of NEAMS Codes to Capture MSR Phenomena

Bao, Feng; Shahbazi, Shayan; Fang, Jun; Fei, Ting; Shaver, Dillon

doi:10.2172/1826681

Cited by 5 publications

(5 citation statements)

References 38 publications

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“…This value is compared in Table 4-5 with the estimated tritium concentration of the primary salt considering tritium retention in the graphite [17]. The calculated value is less than the historic calculation results of 4.29E-7 mol/m 3 [16] for the fuel salt. This discrepancy might be due to a larger portion of the tritium being removed from the fuel salt into the cover gas in the pump bowl than assumed in the historical calculation.…”

Section: Tritium Distribution In the Msrementioning

confidence: 81%

“…The MSRE tritium transport model has been prepared based on the MSRE reactivity insertion test model using SAM previously reported [16]. It consists of the primary loop of the MSRE, which includes a representative core channel, a representative graphite moderator, a heat exchanger, a pump, and pipes connecting major components.…”

Section: Msre Tritium Transport Model Using Sammentioning

confidence: 99%

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Multiphysics Simulations of MSRE with NEAMS Thermal Hydraulics Tools

Cao,

Fang,

Jeong

et al. 2023

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Section: Tritium Distribution In the Msrementioning

confidence: 81%

Section: Msre Tritium Transport Model Using Sammentioning

confidence: 99%

Multiphysics Simulations of MSRE with NEAMS Thermal Hydraulics Tools

Cao,

Fang,

Jeong

et al. 2023

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“…The MSRE facility was operated at ORNL during the 1960s to test steady state and transient behavior of a liquid salt fueled reactor. A model of the facility was built during a previous NEAMS activity as documented in [49] in order to model one of the reactivity insertion tests that were performed in the facility, which is described in [50]. This existing model was modified for this work to include the gas transport model and to demonstrate the gas model behavior for more realistic conditions of interest than those that were used for regression and validation testing.…”

Section: Demonstration Of Gas Transport Model In Msrementioning

confidence: 99%

Development of Integrated Thermal Fluids Modeling Capability for MSRs

Fang

Nunez

et al. 2022

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The DOE Nuclear Energy Advanced Modeling and Simulation (NEAMS) program supports a full range of computational thermal fluids analysis capabilities and code developments for a broad class of light-water and advanced reactor concepts. The research and development approach under thermal fluids technical area synergistically combines three length and time scales in a hierarchal multi-scale approach. To demonstrate the feasibility and capabilities of a multi-scale thermal fluids capability using these codes, a key joint effort has been pursued to develop an integrated systemand engineering-scale thermal fluids analysis capability with the MOOSE-based codes, through integration of SAM and Pronghorn, both based on the MOOSE framework.

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“…An overview was previously provided on the potential role of NEAMS tools in capturing MSR chemistry phenomena [51]. Based on recent code development activities under various technical areas of NEAMS such as Structural Materials & Chemistry, Thermal Hydraulics, and Reactor Physics, a brief updated review is provided below on the current state of NEAMS tools that support multiphysics modeling of chemistry phenomena of molten salt reactors (MSR).…”

Section: Neams Capabilitiesmentioning

confidence: 99%