Integrated Modeling of Fuel Flows in the Plasma and in the Injection and Pumping Systems for the Demo-FNS Fusion Neutron Source

Ananyev, S.S.; Dnestrovsky, A.Yu.; Kukushkin, A.S.

doi:10.21517/0202-3822-2020-43-4-96-109

Cited by 3 publications

(14 citation statements)

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“…In this case, the pellets injected into the plasma consist of pure tritium (S pel D = 0). The parameter In the FC-FNS code, the particle balance is described in the zero-dimensional approximation using the SNB, Spel, and Ssep sources of the particles, assuming different lifetimes correlated with the ASTRA simulations [25].…”

Section: Discussion Of Resultsmentioning

confidence: 99%

“…The SOLPS run results relevant for the core-edge coupling are parameterized to form scalings for the plasma parameters at the separatrix, and these scalings form the boundary conditions for ASTRA [24]. This approach was previously used for analyzing the FC of the DEMO-FNS facility [16,25,26], and in this work, it is used for the FNS-ST facility. To describe adequately in ASTRA the heat and particle fluxes in the bulk plasma, we use the Bohm/gyro-Bohm transport model [27] that takes into account the effects of nonlocal transport.…”

Section: Consistent Model For Calculating Fluxes In the Fuel Cyclementioning

confidence: 99%

“…In the calculations with varying fcore, the isotope composition of the D+T beam was taken unchanged such that fNB T = 0.5. In the FC-FNS code, the particle balance is described in the zero-dimensional approximation using the S NB , S pel , and S sep sources of the particles, assuming different lifetimes correlated with the ASTRA simulations [25].…”

Section: Consistent Model For Calculating Fluxes In the Fuel Cyclementioning

confidence: 99%

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Selection of Fuel Isotope Composition in Heating Injectors of the FNS-ST Compact Fusion Neutron Source

2021

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For the FNS-ST compact neutron source, the dependence of the neutron yield on the tritium content in the bulk plasma is analyzed for the operation of the heating injectors with different isotope compositions of the neutral beams. Self-consistent simulations of the FNS-ST operating regimes are performed using the SOLPS4.3 and ASTRA codes for different densities of the bulk plasma and diffusion coefficients. The FC-FNS code is used to calculate the required fluxes of the fuel components into the plasma provided by different injection systems: the pellet injectors and the neutral beams. In simulations, the plasma density is varied in the range ne = (7–10) × 1019 m−3, and the ratio of the diffusivity to the heat conductivity in the range D/χe = 0.2–0.6. For the scenarios with the D + T or D beams, in the window of the operating parameters, the maximum possible fractions of tritium in the bulk plasma are calculated, and the corresponding neutron yields are obtained. For the regimes with the maximum neutron yield (4.5–5.5) × 1017 s−1, the accumulation of tritium at the site (up to 550 g) is calculated for different heating beams.

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Section: Discussion Of Resultsmentioning

confidence: 99%

Section: Consistent Model For Calculating Fluxes In the Fuel Cyclementioning

confidence: 99%

Section: Consistent Model For Calculating Fluxes In the Fuel Cyclementioning

confidence: 99%

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Selection of Fuel Isotope Composition in Heating Injectors of the FNS-ST Compact Fusion Neutron Source

2021

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“…The updated code version takes into account the selfconsistent core and divertor plasma parameters obtained from joint simulation with the SOLPS4.3 and ASTRA codes. The approach was developed for DEMO-FNS FC simulation in the presence of feedback between the pumping and injection systems, considering the change in the isotopic composition of the near-wall and plasma core [14,28]. In this work, the model is significantly improved and used for advanced analysis.…”

Section: Integrated Modeling Of Core and Divertor Plasmamentioning

confidence: 99%

“…In the FC-FNS code plasma model, we assume that the core plasma receives particles from three sources (the NBI systems, the cryogenic fuel pellets feed systems, and the neutral flux from the SOL region), comparable in contribution to the core density [17,28]. Then the global particle balance in the plasma core can be written in the form…”

Section: Integrated Modeling Of Core and Divertor Plasmamentioning

confidence: 99%

Concept development and candidate technologies selection for the DEMO–FNS fuel cycle systems

et al. 2021

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Within the framework of activities on a pilot industrial hybrid reactor (pilot hybrid plant-PHP) development, the DEMO–FNS fusion neutron source is being designed in Russia. Russian fusion and fission community considers it as the main facility developing prospective nuclear technologies, which should update the results of the ITER researches in the field of physics and control of burning plasma. Progress in the development of the plant and simulations of the fusion fuel cycle allows starting the engineering design of basic fuel cycle systems. In this paper, we consider the new prospective of technological solutions for the tokamak fuel cycle. The possibility of their integration and the analysis of the technology readiness level for them in the Russian Federation are addressed as well. The code simulating the hydrogen isotope flows in a tokamak was significantly upgraded for evaluation of the specific technological solutions as well as for combined modeling of the fuel circulation in the core and divertor plasmas allowing for the pumping, processing, and fuel isotope content control in the plasma. The article describes the core and divertor plasma model used for the calculations and shows the D/T fuel throughput values, which should be provided by the fuel injection systems (NBI and pellets). The dependencies of the HFS and LFS pellet injection frequency necessary for the main plasma supply and ELM control are found for different core and divertor plasma parameters. For the DEMO–FNS core plasma, an operating window has been found in terms of fueling control parameters. It was shown that D and T throughputs of 40–50 Pa·m3 s−1 should be provided by the fuel injection systems (NBI and pellets) to maintain the fusion power up to 40 MW. For the DEMO–FNS core plasma, an operating window defined by the particle confinement times and fuel injection throughputs has been found.

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Calculation of Consistent Plasma Parameters for DEMO-FNS Using Ionic Transport Equations and Simulation of the Tritium Fuel Cycle

Ananyev

Kukushkin

2023

Applied Sciences

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Modeling the D and T fluxes in Fusion Neutron Source based on a tokamak fuel cycle systems was performed consistently with the core and divertor plasma. An indirect integration of ASTRA, SOLPS4.3, and FC-FNS codes is used. The feedback coupling is realized between the pumping and puffing systems in the form of changes in the isotopic composition of the core and edge plasma. In the ASTRA code, instead of electrons, ions were used in the particle transport equations. This allows better estimates of the flows of the D/T components of the fuel that have to be provided by the gas puffing and processing systems. The particle flows into the plasma from pellets, required to maintain the target plasma density <ne> = (6–8) × 1019 m−3 are 1022 particles/s. In the majority of the working range of parameters, additional ELM stimulation is necessary (by ~1-mm3-size pellets from the low magnetic field side) in order to maintain the controlled energy losses at the level δWELM~0.5 MJ. For the starting load of the FC and steady-state operation of the facility, up to 500 g of tritium are required taking into account the radioactive decay losses.

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Integrated Modeling of Fuel Flows in the Plasma and in the Injection and Pumping Systems for the Demo-FNS Fusion Neutron Source

Cited by 3 publications

References 0 publications

Selection of Fuel Isotope Composition in Heating Injectors of the FNS-ST Compact Fusion Neutron Source

Selection of Fuel Isotope Composition in Heating Injectors of the FNS-ST Compact Fusion Neutron Source

Concept development and candidate technologies selection for the DEMO–FNS fuel cycle systems

Calculation of Consistent Plasma Parameters for DEMO-FNS Using Ionic Transport Equations and Simulation of the Tritium Fuel Cycle

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