Verification of Modelica-Based Models with Analytical Solutions for Tritium Diffusion

Rader, Jordan D.; Greenwood, Michael S.; Humrickhouse, Paul W.

doi:10.1080/00295450.2018.1431505

Cited by 16 publications

(10 citation statements)

References 21 publications

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“…In some cases, it has even been assumed that D H + > D 0 H , which could cause signicant error in predicting transport behavior. 20,50 From this work, it is clear that experiments that controlled for speciation, impurities, and corrosion produced more reliable data than those that did not, which was supported by simulation results. Further, the simulations provide insights that allowed understanding of transport behavior at the level of local atomic structure, which would otherwise be difficult to infer from experimental data alone.…”

Section: Implications Of Coupled Hydrogen Diffusion and Chemistry In Molten Saltsupporting

confidence: 61%

The impact of hydrogen valence on its bonding and transport in molten fluoride salts

Lam

Mailoa

et al. 2021

J. Mater. Chem. A

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Section: Implications Of Coupled Hydrogen Diffusion and Chemistry In Molten Saltsupporting

confidence: 61%

The impact of hydrogen valence on its bonding and transport in molten fluoride salts

Lam

Mailoa

et al. 2021

J. Mater. Chem. A

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“…Conventionally, the differences between the diffusion of H * and H ) in molten salt has been ignored due to a lack of information. In some cases, it has even been assumed that / & > / # , which could cause significant error in predicting transport behavior [46] [47]. From this work, it is clear that experiments which controlled for speciation, impurities, and corrosion produced more reliable data than those that did not.…”

Section: Impact Of Hydrogen Diffusion and Chemistry In Molten Saltmentioning

confidence: 90%

The Impact of Hydrogen Valence on Its Bonding and Transport in Molten Fluoride Salts

Lam

Mailoa

et al. 2020

Preprint

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Interest in molten salts has increased significantly over the last decade due to their potential application in various clean-energy technologies including hydrogen generation, solar heat storage, and advanced nuclear power plants. In the development of new molten salt-based fission and fusion systems, controlling hydrogen poses a critical challenge due to its ability to corrode structural materials as 3H+, and its potential to cause significant radioactive release as diffusive 3H0. Yet, the chemistry and transport behavior of the hydrogen species remain poorly understood despite several decades of research. Using ab initio molecular dynamics, we present a coupled examination of hydrogen valence, speciation and transport in the prototypical salts 66.6%LiF-33.3¾F2 (Flibe) and 46.5%LiF-11.5%NaF-42%KF (Flinak). We discovered significant differences between 3H0 and 3H+transport behaviors. 3H+ diffuses 2-4 times slower than 3H0, which can be ascribed to hydrogen bonding and complexation in solution. This work helps explain varying experimental results and provides useful species transport data for designing hydrogen control systems for molten salts.

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“…The TRANSFORM library has been successfully used for a variety of projects, including investigations into the performance of nuclear hybrid energy systems (Greenwood, 2017c;Rabiti et al, 2017) and tritium transport (Rader et al, 2018).…”

Section: Transformmentioning

confidence: 99%

“…Using mass transfer analogies to heat transfer, the tritium is permitted to flow from the primary fuel loop to the primary coolant loop and from the primary coolant loop to the balance of plant through the respective heat exchangers. Further details on the methodology can be found in (Rader et al, 2018). Other major components accountable for tritium leaving the primary fuel loop, or tritium management systems, may be incorporated in the future.…”

Section: Tritium Transportmentioning

confidence: 99%

Molten Salt-Fueled Nuclear Reactor Model for Licensing and Safeguards Investigations

Greenwood¹

2019

Linköping Electronic Conference Proceedings

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Fluid-fueled nuclear reactors, particularly molten salt reactors (MSRs), have recently gained significant interest. As with all reactors, modeling and simulation are key factors for advanced reactor design and licensing and will be required for the deployment of MSRs. However, there are significant gaps between simulation capabilities and system behavior for MSRs. This paper presents the system model of an MSR that is based on the Molten Salt Demonstration Reactor. The model includes important physics specific to MSRs, such as fission product and tritium transport and reactivity feedback. Keywords: molten salt reactors, salt-fueled, nuclear (3) definition of modeling conventions for model and component development, and (4) establishment of user interfaces and support tools to facilitate simulation development and analysis (R. Hale et al., 2015; R. E.

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Verification of Modelica-Based Models with Analytical Solutions for Tritium Diffusion

Cited by 16 publications

References 21 publications

The impact of hydrogen valence on its bonding and transport in molten fluoride salts

The impact of hydrogen valence on its bonding and transport in molten fluoride salts

The Impact of Hydrogen Valence on Its Bonding and Transport in Molten Fluoride Salts

Molten Salt-Fueled Nuclear Reactor Model for Licensing and Safeguards Investigations

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