Tokamak D-T neutron source models for different plasma physics confinement modes

Fausser, C.; Puma, A. Li; Gabriel, Franck; Villari, R.

doi:10.1016/j.fusengdes.2012.02.025

Cited by 70 publications

(22 citation statements)

References 10 publications

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“…For this reason, a dedicated global neutron source model has been developed to simulate the actual neutron volumetric source of a fusion reactor (e.g. [10]), assumed (due to MHD equilibrium properties) to be constant along the plasma magnetic surfaces (MS), as depicted in Fig. 4 with black dashed lines.…”

Section: Neutron Source Definitionmentioning

confidence: 99%

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Identification of blanket design points using an integrated multi-physics approach

Spagnuolo

Franza

Fischer

et al. 2017

Fusion Engineering and Design

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The Breeding Blanket (BB) is one of the key components for a fusion reactor. It is expected to sustain and remove considerable heat loads due to the heat flux coming from the plasma and the nuclear power deposited by the fusion neutrons, to breed the tritium consumed in the fusion reactions and to shield the Vacuum Vessel (VV) PROCEDUREThe approach has been articulated in the following phases: 1. Import of the reference from CAD into ANSYS DesignModeler.2. Geometry decomposition (slicing and reparation of sharp angles, slivers, spikes, etc.) and geometry conversion into MCNP legacy Constructive Solid Geometry (CSG).3. Performing of neutronic analysis.4. Mapping of power density calculations into ANSYS Mechanical. GEOMETRY DECOMPOSITIONIt has been sliced in order to have simple configuration suitable for the CSG representation;The VV, the gap between the VV inner wall and the BB have been introduced;The cooling channels have been filled to model the coolant;The corners of the cooling channels have been squared; An enclosure has been used to shape the Graveyard. CSG GEOMETRY CONVERSION AND NEUTRONIC ANALYSISThe elaborated CAD model has been exported generating a geometric input for neutronic analysis based on the CSG;It has been verified the conservation of the volumes using the stochastic estimation on the ray tracing;Total volume average error equal to 0.01%;Maximum volume error between 0.811% and -0.725%;It has been used a mono-energetic test source biased in the angular distribution;The reflecting boundary conditions have been imposed in the poloidal direction;It has been modelled the VV in order to take into account of the neutron back scattering;The power density deposition has been assessed defining a fmesh-tally with 1.88 million of elements. MAPPING OF HEAT GENERATIONA mesh sensitivity analysis has been carried out to determine an appropriated spatial discretization;A mesh composed of~6.8·10 6 nodes connected in~2.8·10 6 tetrahedral elements has been chosen allowing an accurate interpolation of the data between MCNP and ANSYS;A complete coupling has been performed admitting to use the neutronic outcomes for thermal-hydraulic and thermo-mechanical calculations. CONCLUSIONAt theoretical-computational research campaign has been performed by KIT to create an integrated multiphysics approach to be used for the identification and analysis of BB design points.A test model has been realised accomplishing the complete coupling between the software.The correctness and applicability of the approach have been demonstrated, and the great advantages derived from using the same geometry for all the analyses involved in the design of the BB have been also introduced.CAD ANSYS ModelEditor MCNP5/6 ANSYS Mechanical

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Section: Neutron Source Definitionmentioning

confidence: 99%

“…The neutron source is therefore sampled on the j-th volume (or cell) based on the probability p j , which is calculated considering a given source density distribution function S(a) [10]. The probability p j is defined by the ratio of the neutron yield in cell j (a i ≤ r ≤ a i+1 ) and the neutron yield.…”

Section: Neutron Source Definitionmentioning

confidence: 99%

Identification of blanket design points using an integrated multi-physics approach

Spagnuolo

Franza

Fischer

et al. 2017

Fusion Engineering and Design

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“…Neutron sources were sampled from a probability distribution of 14 MeV neutron source S(r) [8] according to: …”

Section: Neutron Wall Loadingmentioning

confidence: 99%

Preliminary neutronics design and analysis of helium cooled solid breeder blanket for CFETR

Chen

et al. 2015

Fusion Engineering and Design

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“…5). In both codes the neutron source input was produced by the TRANGEN code [12]. TRANGEN generates plasma neutron source (in L or H plasma confinement modes) in SDEF card format for MCNP and in TABULATED format for TRIPOLI.…”

Section: Tripoli-4mentioning

confidence: 99%

Monte Carlo tools evaluation for nuclear analyses of the European DEMO

Jaboulay

Damian

Aiello

et al. 2015

Fusion Engineering and Design

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Tokamak D-T neutron source models for different plasma physics confinement modes

Cited by 70 publications

References 10 publications

Identification of blanket design points using an integrated multi-physics approach

Identification of blanket design points using an integrated multi-physics approach

Preliminary neutronics design and analysis of helium cooled solid breeder blanket for CFETR

Monte Carlo tools evaluation for nuclear analyses of the European DEMO

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