The solution of a simulation problem and the analysis of three-dimensional temperature field in a heating element of transformer type are considered. The design of a three-phase heating element with ...a spatial magnetic system is presented. The features of model construction using ANSYS software package are described. The results of simulation of temperature field in the heating element with the power of 25 kW are shown and analyzed. It is revealed that the temperature field in the area of primary winding is distributed unevenly and there are regions of local overheating. A heat removal from these regions is carried out by two main paths. The heat removal intensity and the distribution of heat fluxes depend on the current density in the jumper, which closes the elements of the secondary winding. Taking this into account, recommendations for selecting the electromagnetic loads in the active parts of the heating element and improving the design of electrical equipment are presented. To justify the modes of operation of the heating element as a part of heating unit of a stand-alone heat-supply system, the interrelation between the flow rate of the heat-transfer agent and the power of the heating element was revealed, which makes it possible to limit the maximum temperature in areas of local overheating and prolong the operation life of electrical equipment.
In the IFMIF-DONES neutron source a single accelerator line delivers 125 mA of deuterons at 40 MeV to a flowing liquid lithium target with a free surface facing the deuteron beam.
Neutrons with ...fusion-relevant spectrum are generated by a stripping reaction and used for material samples irradiation.
This report presents a numerical thermal–hydraulic and structural analysis using updated design of the target system and neutronics analysis results. Simulation scope includes the target assembly, vacuum chamber with beam ducts, outlet channel, quench tank vessel and connecting elements.
Simulations have been conducted with the commercial CFD code Simcenter Star-CCM + . The computational domains consist total of 47.4x106 fluid and 14x106 structure cells.
The following aspects have been analyzed:•Temperature distribution in lithium and target system structure during beam-on operation;•Transient mixing of lithium in the quench tank with temperature change during the beam switch-on phase.•Thermal displacements and stresses in the TA and QT structures.Simulations using the new distribution of nuclear heating show no significant changes in the temperature field in liquid lithium. Calculated unwanted temperature hotspots in the target structure demonstrate the need for optimization of the target design.
Relations obtained from an analysis of published data and as a result of mathematical modeling of a glass furnace are presented for calculating the heat flux density into the environment from the ...outer surfaces of the enclosure of an industrial furnace — sidewalls, roof, and hearth. On the basis of a comparative analysis of these relations for a glass furnace recommendations are formulated for selecting and using relations for calculating the coefficients of heat emission from the outer walls of the enclosure for the purpose of making a better determination of the heat balance of a furnace.
•McCad – software tool developed at KIT for the automatic conversion of CAD models into the geometry representation of Monte Carlo particle transport codes.•Open source software running under the ...Linux operating system and utilizing Open Cascade CAD kernel with the Qt4 libraries for the graphical user interface (GUI).•Converted geometry models can be output in the syntax of MCNP and TRIPOLI of the Monte Carlo codes.•Related visualization capabilities, based on coupling of McCad with the ParaView software, allow to overlay mesh tally distributions to the CAD geometry.•McCad applied to solve fusion neutronics problems of ITER and the IFMIF neutron source.
The McCad geometry conversion tool has been developed at KIT to enable the automatic conversion of CAD models into the semi-algebraic geometry representation as utilized in Monte Carlo particle transport simulations. McCad is entirely based on open source software, it is running under the Linux operating system and utilizes the Open Cascade CAD kernel with the Qt4 libraries for the graphical user interface (GUI). The converted geometry models can be output in the syntax of the Monte Carlo codes MCNP and TRIPOLI. Related visualization capabilities are based on the coupling of McCad with the ParaView software and allow to overlay mesh tally distributions to the CAD geometry. This enables perspective 3D representations or animations on the CAD geometry. The paper presents the current status of the McCad approach and its implementation, and discusses its capabilities, limitations as well as future development needs. The use of McCad for fusion neutronics applications is illustrated on the examples of the MCNP model generation for ITER Test Blanket Modules (TBM) and the test cell facility of the IFMIF neutron source including Monte Carlo shielding calculations using the converted models.
Neutronics for equatorial and upper ports in ITER Serikov, A.; Fischer, U.; Henderson, M. ...
Fusion engineering and design,
October 2013, 2013-10-00, 20131001, Letnik:
88, Številka:
9-10
Journal Article
Recenzirano
•ITER neutronics calculations for Diagnostic Equatorial Port Plug (EPP) and Electron Cyclotron Heating Upper Launcher (ECHUL).•Activation and radiation shielding calculations have been performed ...using the MCNP5, FISPACT-2007, and R2Smesh codes.•Dominant effect of radiation streaming along the port plug gaps was recognized.•An optimized double labyrinth was recommended for the current EPP design.•Neutronics modelling assumptions significantly affect fluxes and doses inside the ITER port interspaces.
Specific neutronics features of the ITER equatorial and upper ports are discussed in this paper as related to the design development of Diagnostic Equatorial Port Plug (EPP) and Electron Cyclotron Heating Upper Launcher (ECHUL). The focus is on the EPP analysis. Neutronics analyses are based on new calculation results of neutron/photon fluxes, nuclear heating, neutron damage and shutdown dose rates. The results were obtained with the radiation transport code MCNP5, the activation code FISPACT-2007, and the Rigorous 2 Step mesh-based (R2Smesh) interface code which allows to provide shutdown dose rate distributions with high spatial resolution. It was revealed that neutron flux levels in the port access areas, the resulting activation of the port materials and the equivalent radiation doses imposed to work personnel after ITER shutdown are strongly dependent on the openings in the port shielding blocks. For the ECHUL in the upper port, neutron fluxes have been calculated for an updated ITER model and compared with previous results. This work reveals substantial radiation cross-talk effects between the lower, the equatorial and the upper ITER ports and provides fundamental results which can be utilized for further investigations of suitable design options of ITER ports.
► Systematic neutronics analyses were conducted to assess the ITER Equatorial Port Plug radiation shielding performance. ► Shielding optimization was achieved by parametric analyses of several design ...variants using the MCNP5, FISPACT-2007, and R2Smesh codes. ► Dominant effect of radiation streaming along the port plug gaps was recognized. ► Combination of the gap labyrinths and streaming stoppers or rails reduces shutdown doses by 2 orders of magnitude. ► Using the proposed shielding, the shutdown dose in the ITER port interspace is less than the personnel access limit of 100μSv/h.
This paper addresses neutronics aspects of the design development of the Diagnostic Generic Equatorial Port Plug (EPP) in ITER. To secure the personnel access at the EPP back-end interspace, parametric neutronics analyses of the EPP radiation environment have been performed and practical shielding solutions have been found. Radiation transport was performed with the Monte Carlo MCNP5 code. Activation calculations were conducted with the FISPACT-2007 inventory code. The R2Smesh approach was applied to couple transport and activation calculations. Newly created EPP local MCNP5 model was devised by extracting the EPP and adjacent blanket modules from the ITER Alite-4.1 model with proper modification of the EPP geometry in accordance with recent 3D CAD CATIA model. The EPP local model reproduces the EPP neutronically important features and allows investigation of the EPP neutronics effects in isolation from all other ITER components. Thorough EPP parametric analyses revealed dominant effect of gaps around EPP and several EPP design improvements were implemented as the outcomes of the analyses. Gap labyrinths and streaming stoppers inserted into the gaps were shown are capable to reduce the shutdown dose rate which is below the 100μSv/h limit of personnel access and by 2 orders of magnitude less than the value in the model with straight gaps.
The thick target inverse kinematics (TTIK) approach was used to measure excitation functions for the elastic
O (
) scattering at the initial
O beam energy of 54.4 MeV. We observed strong peaks ...corresponding to highly excited
-cluster states in the
Ne excitation energy region of 8–16 MeV, which have never been investigated before. Additional tests were done at a
O beam energy of 56.4 MeV to estimate a possible contribution of resonance inelastic scattering.
Thermochemical recuperation of exhaust gases heat can be a promising way to save energy when it comes to high-temperature plants heated by natural gas, for example glass melting furnaces. This ...technology can help to save up to 10–25% of energy without affecting other parameters of the process.
Schemes of glass melting furnaces with various options for thermochemical recuperation were simulated using Mathcad code and Aspen Plus code. It is shown that the dependence of specific primary energy consumption on the volume fraction of recirculated exhaust gases used as an oxidant for the reforming process is non-monotonic and has a minimum at the range of values 0.19–0.22 of mentioned volume fraction.
Determination of the oxidant flow coefficient for the reforming process for all considered options of thermochemical recuperation were suggested, as well as method of that calculation. In the industrial plant with reforming based on the recirculated exhaust gases transition to the optimal value of this coefficient (close to 1.00) is considered to be energy-saving, which reduces fuel consumption by 16% and reduces environmental pollution.
Use of economic evaluation of environmental pollution will allow to choose the scheme of thermochemical recuperation more efficiently.
•Study of glass furnaces with options of thermochemical recuperation was performed.•The method of calculation the oxidant flow coefficient for the reforming process.•A technique of ensuring minimum of the primary energy consumption.
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