Integration of the Full Tokamak Reference Model with the Complex Model for ITER Neutronic Analysis

Yang, Jinan; Wilson, S. R.; Mosher, Scott W.; Radulescu, Georgeta

doi:10.1080/15361055.2018.1493325

Cited by 14 publications

(26 citation statements)

References 3 publications

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“…A more in-depth analysis can be performed to assess the effect to TBR and specific activity of other parameters besides vacuum vessel material. Figure 4 shows the distribution of the metrics for each vacuum vessel material; colors denote the 6 Li enrichment (left) and beryllium thickness (right), while different markers indicate first wall (tungsten) layer thickness. This figure shows the general trend of metrics with the change in the parameters.…”

Section: Resultsmentioning

confidence: 99%

“…The thicknesses of the first wall, the beryllium neutron multiplier, and the vacuum vessels were perturbed. Additionally, the 6 Li enrichment and the selection of vacuum vessel materials was explored. The coolant channel thickness remains constant at 2 cm.…”

Section: Parametersmentioning

confidence: 99%

“…The response metrics considered for this work are the TBR and vacuum vessel specific activity after 2 EFPY and one day of cooling to allow very short-lived isotopes to decay out. These two variables depend not only on the flux magnitude but also on the flux spectrum because important reactions, like the (n,Xt) reaction of 6 Li , have energy-dependent cross sections. This work also explores the different responses from high breeding salt enrichment (90% 6 Li ) and natural enrichment (7.5% 6 Li ) and the integral effects of layer thicknesses.…”

Section: Response Spacementioning

confidence: 99%

“…These two variables depend not only on the flux magnitude but also on the flux spectrum because important reactions, like the (n,Xt) reaction of 6 Li , have energy-dependent cross sections. This work also explores the different responses from high breeding salt enrichment (90% 6 Li ) and natural enrichment (7.5% 6 Li ) and the integral effects of layer thicknesses. Depending on the enrichment, the TBR of the system responds differently to the flux energies (figure 2).…”

Section: Response Spacementioning

confidence: 99%

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Integral analysis of the effect of material dimension and composition on tokamak neutronics ^*

Bae,

Young,

Borowiec

et al. 2024

Nucl. Fusion

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The neutronics performance of a tokamak has been identified as an important factor in designing a fusion power plant. The design of the tokamak should not only meet operational parameters such as sufficient tritium breeding, but also safety parameters such as low structural material activation. This paper investigates the impacts of the neutronics metrics for the ARC-class tokamak, a compact tokamak with an immersion blanket, by perturbing the first five layers of structural material - first wall, inner vacuum vessel, coolant salt channel, neutron multiplier, and outer vacuum vessel. The goal of this work is to provide insight into shaping and scaling the flux on each layer to obtain optimized operational and safety metrics through quantification of the responses from each perturbation.Results show that increased first wall thickness can increase the tritium breeding ratio (TBR) in specific configurations with high Li6 enrichments and that vacuum vessels decrease TBR for low-Li6 enrichment configurations. It was also found that the neutron multiplier can either increase or decrease TBR depending on the configuration. The response of metrics to the change in layer thickness and enrichment also varies depending on the vacuum vessel material. The integral impacts of Li6 enrichment, layer thicknesses, and vacuum vessel material choice are investigated and presented in this paper.

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Section: Resultsmentioning

confidence: 99%

Section: Parametersmentioning

confidence: 99%

Section: Response Spacementioning

confidence: 99%

Section: Response Spacementioning

confidence: 99%

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Integral analysis of the effect of material dimension and composition on tokamak neutronics ^*

Bae,

Young,

Borowiec

et al. 2024

Nucl. Fusion

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“…MCNP [11] is a general-purpose Monte Carlo (MC) particle transport tool that is widely used for fusion neutronics applications [12], including ITER [13][14][15][16][17]. Traditionally, the geometry in MCNP uses surfaces such as planes, spheres, cones, and tori, which can be combined to create solids of arbitrary complexity.…”

Section: Mcnpmentioning

confidence: 99%

Impact of fusion reactor neutronics modeling for transmutation and thermal feedback ^*

Bae,

Borowiec,

Sircar

et al. 2023

Nucl. Fusion

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Fusion neutronics calculations provide important metrics pertinent to fusion reactor operations, such as tritium breeding ratios and data on heat deposition, material activation, and damage. Because of the high computational burden required to generate a high-fidelity Monte Carlo simulation of a 3D fusion reactor, various assumptions are made to reduce computational time by simplifying the reactor model or the calculation iteration. This paper explores the impact of fusion neutronics metrics such as the tritium breeding ratio and decay heat of structural materials based on assumptions of material composition in the fusion reactor and temperature modeling of materials. Results show that for compact tokamaks with high power and long operational cycles, the transmutation of structural materials is significant enough to cause a substantial change in the flux spectrum and decrease the tritium breeding ratio (TBR) by 3.63% after 2 years of full power operation. Additionally, assuming a constant temperature and material density can impact the TBR calculations up to 3%.

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Singular value decomposition of adjoint flux distributions for Monte Carlo variance reduction

Biondo

Evans

Davidson

et al. 2020

Annals of Nuclear Energy

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Integration of the Full Tokamak Reference Model with the Complex Model for ITER Neutronic Analysis

Cited by 14 publications

References 3 publications

Integral analysis of the effect of material dimension and composition on tokamak neutronics ^*

Integral analysis of the effect of material dimension and composition on tokamak neutronics ^*

Impact of fusion reactor neutronics modeling for transmutation and thermal feedback ^*

Singular value decomposition of adjoint flux distributions for Monte Carlo variance reduction

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Integration of the Full Tokamak Reference Model with the Complex Model for ITER Neutronic Analysis

Cited by 14 publications

References 3 publications

Integral analysis of the effect of material dimension and composition on tokamak neutronics *

Integral analysis of the effect of material dimension and composition on tokamak neutronics *

Impact of fusion reactor neutronics modeling for transmutation and thermal feedback *

Singular value decomposition of adjoint flux distributions for Monte Carlo variance reduction

Contact Info

Product

Resources

About

Integral analysis of the effect of material dimension and composition on tokamak neutronics ^*

Integral analysis of the effect of material dimension and composition on tokamak neutronics ^*

Impact of fusion reactor neutronics modeling for transmutation and thermal feedback ^*