Neutronic predesign tool for fusion power reactors system assessment

Jaboulay, Jean-Charles; Puma, A. Li; Arroyo, Javier Martínez

doi:10.1016/j.fusengdes.2013.05.082

Cited by 12 publications

(6 citation statements)

References 17 publications

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“…with R nt = g Σ g n→T φ g indicating the local tritium production rate, Σ g n→T the macroscopic tritium breeding reactions from neutron captures of 6 Li and 7 Li atoms, D BZ the breeding zone (BZ) domain and B p ∝ P fus the tritium burn-up in the plasma.…”

Section: A 1d Model For the Radiation Transport Across The Physical R...mentioning

confidence: 99%

“…In the HCPB blanket, the breeding material (∼20% vol in the BZ region) is composed of a ceramic breeder mixture of Li 4 SiO 4 + 35 mol% Li 2 TiO 3 (with 60% 6 Li enrichment) embedded in prismatic blocks of Be 12 Ti acting as neutron multiplier (∼55% vol). The low-activation Eurofer steel is used as structural material and its volumetric composition in the BZ is approximately 15% vol.…”

Section: Input Configuration Of the Eu-demo 2017 Baselinementioning

confidence: 99%

“…Different fusion systems are presently available in the EU and worldwide to support the design of fusion reactors, each characterized by different features, architectures and scopes. The key presently-available fusion SCs are PROCESS [3,4], SYCOMORE [5][6][7], ARIES systems code [8], KAERI system code [9] and JAERI system code [10]. These tools aim to explore one (or more) reactor configurations that simultaneously fulfil the plasma physics operational limits, the engineering constraints, and the plant requirements.…”

Section: Introductionmentioning

confidence: 99%

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MIRA: a multi-physics approach to designing a fusion power plant

et al. 2022

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Fusion systems codes are deployed to produce the baseline of the European fusion power reactor (DEMO) within its conceptual design. A DEMO baseline is mostly defined by a radial/vertical reactor sketch and major reactor parameters, such as fusion and net electric power, magnetic fields, and plasma burn time. A baseline shall also meet a set of prescribed reactor requirements, constraints, and architectural features. According to the conceptual design workflow implemented within the EU-DEMO programme, the output from the systems code is transferred to the detailed physics and engineering design codes. Presently-available fusion systems codes rely on rather basic physics and engineering models (mostly at zero or one-dimensional level). The design codes, instead, are very detailed but run on much longer computing times. To fill the gap between systems and design codes, the multi-fidelity systems/design tool MIRA - Modular Integrated Reactor Analysis - has been recently developed. MIRA incorporates the physics and the engineering insights of the utmost domains of tokamak reactors and relies on a higher spatial resolution, spanning from 1D up to 3D modelling frames. The MIRA approach has been applied to the DEMO 2017 baseline, generated by the EU reference systems code PROCESS and used as input to MIRA. In the paper, the architectural and mathematical insights of the MIRA package are described, along with an EU-DEMO 2017 baseline analysis.

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Section: A 1d Model For the Radiation Transport Across The Physical R...mentioning

confidence: 99%

Section: Input Configuration Of the Eu-demo 2017 Baselinementioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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MIRA: a multi-physics approach to designing a fusion power plant

et al. 2022

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“…The present module only uses fit functions derived from more advanced neutronics calculations. More refined neutronics using neural networks will be implemented in the near future [18,19].…”

Section: Blanket Modulementioning

confidence: 99%

DEMO reactor design using the new modular system code SYCOMORE

et al. 2015

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A demonstration power plant (DEMO) will be the next step for fusion energy following ITER. Some of the key design questions can be addressed by simulations using system codes. System codes aim to model the whole plant with all its subsystems and identify the impact of their interactions on the design choices. The SYCOMORE code is a modular system code developed to address key questions relevant to tokamak fusion reactor design. SYCOMORE is being developed within the European Integrated Tokamak Modelling framework and provides a global view (technology and physics) of the plant. It includes modules to address plasma physics, divertor physics, breeding blankets, shield design, magnet design and the power balance of plant. The code is coupled to an optimization framework which allows one to specify figures of merit and constraints to obtain optimized designs. Examples of pulsed and steady-state DEMO designs obtained using SYCOMORE are presented. Sensitivity to design assumptions is also studied, showing that the operational domain around working points can be narrow for some cases.

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“…This loop, described in appendix A, also ensures consistent boundary conditions between the SOL and the core plasma. A surrogate model trained on advanced neutronics calculations [4,5] computes the thickness of the tritium breeding blankets (based on helium-cooled lithium lead-HCLL technology) necessary to achieve the required tritium breeding ratio (TBR-number of tritium atoms produced per fusion neutron). It also calculates the shield thickness needed to protect the inner leg of the toroidal field coil from excessive neutron flux.…”

mentioning

confidence: 99%