Thermodynamic analysis and simulation for gas baffle entrance collimator of EAST-NBI systembased on thermo-fluid coupled method

Thermodynamic analysis and simulation for gas baffle entrance collimator of EAST-NBI systembased on thermo-fluid coupled method 1 corresp first-author Corresponding author. E-mail address: palytao@ipp.ac.cn Corresponding author. E-mail address: palytao@ipp.ac.cn palytao@ipp.ac.cn 1 1 Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, China Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, China The world's first full Experimental Advanced Superconducting Tokamak (EAST) is designed with the auxiliary heating method of neutral beam injection (NBI) system. Beam collimators are arranged on both sides of the beam channel for absorbing the divergence beam during the beam transmission process in the EAST-NBI system. The Gas Baffle Entrance Collimator (GBEC) is a typical high-heat-flux component located at the entrance of gas baffle. An efficient and accurate analysis of its thermodynamic performance is of great significance to explore the working limit and to ensure safe operation of the system under a high-parameter steady-state condition. Based on the thermo-fluid coupled method, thermodynamic analysis and simulation of GBEC is performed to get the working states and corresponding operating limits at different beam extraction conditions. This study provides a theoretical guidance for the next step to achieve long pulse with high power experimental operation, and has an important reference to ensure the safe operation of the system. Neutral beam injection High-heat-flux component Beam collimator Thermo-fluid coupled method Thermo-dynamic analysis 1 Introduction 1 Neutral beam injection (NBI) is an important auxiliary heating method for Tokamak devices, with high heating efficiency and clear heating mechanism. Two sets of NBI system have been used in the Experimental Advanced Superconducting Tokamak (EAST) in China [ 1 1 - 4 4 1-4 ] . Plasma generated in the ion source has uniform ion density and space charge effect of particles, and the beam will continue to diverge during the process of beam transmission [ 5 5 , 6 6 ] . To prevent instability of the system caused by the divergent beam bombardment to the main components inside the vacuum chamber, collimators to absorb the divergent beam are required for various components and arranged around the beam channel. Varieties of temperature measurement devices are arranged to get temperature profile and introduce working status of the ion source and the extraction system. The beam collimators around the beam channels of NBI system are mainly located at the ion source exit, the entrance of gas baffle (Gas Baffle Entrance Collimator, GBEC), and the entrance and outlet of deflection system. How to confirm the reliability of these heat transfer structures in design conditions is important for system safe operation. The designs of high-heat-flux (HHF) components are optimized on the basis of thermo-fluid analysis. Considering the characteristics of different HHF components, several authors used the design-by-analysis approach with help of 3D computational fluid dynamic codes and achieved the hypervapotron thermal hydraulic condition [ 7 7 - 9 9 7-9 ] . In the International Thermonuclear Experimental Reactor project (ITER), the supporting structures of plasma-facing components are designed on the basis of thermal hydraulic analysis [ 10 10 - 11 11 10-11 ] . 3D thermal thermo-hydraulic analysis with the flows-solid coupling heat conduction model have been carried out for the cooling structure of EAST tungsten divertor, the water cooled ceramic breeder blanket for Chinese Fusion Engineering Test Reactor [ 12 12 ] , and the typical HHF ion dump of EAST-NBI system [ 13 13 ] . In this paper, according to the engineering requirements and the structural design features of the GBEC in the EAST-NBI system, the thermo-fluid coupling analysis and 3D simulation of the beam collimator under different beam extraction parameters are presented. The results provide a theoretical guidance of operation ability for the components in the long pulse quasi-steady-state experimental conditions. 2 GBEC of the EAST-NBI system 1 Figure 1 Figure 1 shows the GBEC of EAST-NBI system. It is located at the neutralizer outlet and upstream of the deflection magnet, between Cryopumps 1 and 3. A gas baffle is to form differential pressure distribution in the main vacuum chamber, so as to assures the beam transmission. The beam collimator uses the cooling tubes welded within the main structure by considering the thermal inertia principle, and is suitable for assembling and disassembling of the NBI system. The collimator is composed of four plates ( Fig.1b Fig.1b ). External frame is sized at 300 mm × 600 mm, while the internal cavity is sized at 150 mm × 470 mm. The two sizes can be properly adjusted by considering beam divergence of system. The oxygen free copper plates of 50 mm thick are built with stainless steel tubes of Φ 12.5 mm to flow cooling water. In order to measure the energy deposition on the GBEC with the water flow calorimetry (WFC) system [ 14 14 ] , the SS tubes adopt in series structure with one inlet and one outlet. According to previous beam transmission theoretical research and experiment, the energy deposition value on the four target plates is about 2.33% of the total beam energy at the entrance of the gas baffle [ 15 15 ] , and the beam intensity distribution of GBEC is shown in Fig. 2 Fig. 2 . 3 Numerical model of thermo-fluid coupled analysis of GBEC 1 In this paper, the structure model is simplified and assumed as follows: (1) The fluid is a steady-state in-compressible flow with no heat source inside; (2) Only the walls facing the beam are subjected to the bombardment of particle energy, and the natural convection and thermal radiation are neglected; (3) The contact thermal resistance between the tube wall and the plate is considered. Based on these assumptions, the governing equations for turbulence and convective heat transfer of GBEC can be established. Details of the equations and corresponding algorithm by the finite volume method can be found in Ref.[ 16 16 ]. Here, turbulent numerical simulation is carried out by adopting the standard k – ε two equation viscous model. For describing the flow in the near wall region accurately, the wall function method is introduced [ 17 17 ] . Mesh quantity is a key factor affecting the calculation, and the GBEC is divided into four pieces: two side plates and the upper and down plates ( Fig.1b Fig.1b ), which are calculated one by one. The grid of geometric structure is shown in Fig.3 Fig.3 . The T grid mesh type is used for the main body of plates and the cooling tube, and the hexahedral mesh is adopted in the fluid region with encrypted boundary layer [ 18 18 - 20 20 18-20 ] . Through the grid independence verification, the grid number is about 1 million, which can meet the precision of calculation requirement. According to the flow process of cooling water in Fig.1(b) Fig.1(b) , the outlet parameters of former plate is equivalent to the inlet value of the next one, and so forth. The boundary conditions are: inlet pressure of the left plate, 0.7 MPa at 20℃; outlet pressure of the right side plate, 0.1 MPa (the same as outlet boundary). The temperature-dependent physical parameters used in the calculation are listed in Table 1 Table 1 . During the simulation process, the Under-Relaxation factors are 0.3 for pressure, 1.0 for density, 1.0 for body force, 0.5 for momentum, 0.3 for turbulent kinetic energy, 0.3 for turbulent dissipation rate and 0,5 for energy, To keep the computational stability and avoid shaking of the residual curve, the inlet boundary of cooling water is chosen to initialize the solution of flow field. For the transient simulation process, the fixed time stepping method is used, in time step size of 0.01 s. 1 1 Material physical parameter 1 1 Value at 293.15 K 1 1 Relational expression as a function of temperature [ 21 21 ] 1 1 Specific heat of water (J·kg −1 ·K −1  ) 1 1 4180 1 1 C p =10608.880−55.736 T +0.159 T 2 −1.494×10 −4 T 3 1 1 Density of water (kg ·m −3  ) 1 1 998.5 1 1 ρ =150.993+7.544 T −0.021 T 2 +1.822×10 −5 T 3 1 1 Thermal conductivity of water  (W·m −1 ·K −1  ) 1 1 0.599 1 1 λ =−0.514+0.005 T −3.357×10 −6 T 2 −6.223×10 9 T 3 1 1 Viscosity coefficient of water (kg·m −1 ·s −1 ) 1 1 0.001006 1 1 μ =0.112−9.515×10 −4 T +2.725×10 −6 T 2 −2.611×10 −9 T 3 1 1 Specific heat of copper  (J·kg −1 ·K −1  ) 1 1 390 1 1 C p =372.541+0.041 T +4.280×10 −5 T 2 1 1 Density of copper (kg·m −3 ) 1 1 8920 1 1 ⸻ 1 1 Thermal conductivity of copper (W·m −1 ·K −1 ) 1 1 390 1 1 λ =421.272−0.072 T +2.650×10 −6 T 2 1 1 Specific heat of 316 SS (J·kg −1 ·K −1 ) 1 1 502.48 1 1 ⸻ 1 1 Density of stainless 316 SS (kg·m −3 ) 1 1 8030 1 1 ⸻ 1 1 Thermal conductivity of 316 SS (W·m −1 ·K −1 ) 1 1 16.27 1 1 ⸻ 4 Results and Discussions 1 In order to check whether the GBEC can meet the design requirements of the EAST-NBI in its long pulse operation, heat transfer performance under different beam extraction conditions is numerically simulated. The beam extraction power, Δ P , is calculated by Δ P = IV , where, V is the high voltage loading for extraction, and I is the beam current extracted. The power depositions under high voltage of 50–80 kV and beam current of 33.5–67.9 A are shown in Table 2 Table 2 . 1 1 High voltage (kV) 1 1 Beam current (A) 1 1 Deposited power (MW) 1 1 50 1 1 33.5 1 1 0.039 1 1 60 1 1 44.1 1 1 0.062 1 1 70 1 1 55.6 1 1 0.090 1 1 80 1 1 67.9 1 1 0.126 4.1 Steady state analysis 2 Steady state analysis is carried out to investigate whether the structure can be well operated under steady state, i.e. the highest temperature on the plate surface does not exceed the softening temperature of the material. The temperature profile of steady state analysis under different beam extraction conditions are shown in Fig.4 Fig.4 . The results show that the four plates of GBEC can bear different heat powers deposited. At beam extraction voltage of 80 kV, the deposited power on the GBEC is about 0.126 MW, corresponding maximum temperature of 694 K for the upper plate and 709 K for the down plate, much more than the soften temperature of oxygen free copper (573 K). In this case, the thin-wall SS cooling tubes are likely to break down, and water to leak At 70 kV, the maximum temperatures of the upper (613 K) and down plates (625 K) also exceeded the temperature limit; whereas the maximum temperatures of the side plates are 510 and 493 K at 80 kV, and 465 and 425 K at 70 kV. So, when the beam extraction voltage is no more than 60 kV, the maximum temperature can be better controlled under the design limit of 573 K. 4.2 Transient analysis 2 According to the steady state simulation results, the transient analysis is carried out for the upper and down plates at 70 and 80 kV to confirm the operation potential under 100s pulse length. The maximum temperatures of the heat-load surface of upper and down plates of GBEC at 70 and 80 kV, verse the pulse length are shown in Fig. 5 Fig. 5 . According to the soften temperature of oxygen free copper (573 K), at 80 kV, the longest working pulse length of the upper and down plates is only 30.7 and 29 s, respectively; while at 70 kV, they are 85 and 75 s, respectively. As a result, for the upper and down plates, the best working beam extraction voltage must less than 60 kV to reach the steady state operation from the view of heat transfer. Without changing heat transfer structure of GBEC, for steady-state operation at beam extraction voltage of 70 and 80 kV, the main body material of the plates should be replaced by CuCrZr, the softening temperature of which is 723 K. 5 Conclusion 1 Based on the thermo-fluid coupled method and near-wall function treatment model, the thermodynamic analysis and simulation of the three-dimensional GBEC is established to get the working states at different beam extraction conditions. From the numerical simulation results, at beam extraction voltage is no more than 60 kV, the cooling structure based on the principle of thermal inertia can effectively achieve the temperature control to reach the steady state operation of EAST-NBI system, but if the beam extraction voltage is over 60 kV, the material of the main body need to be replaced by CuCrZr in order to fulfill the steady state operation without changing cooling structure. This study provides a theoretical guidance for the next step to carry out long pulse high power quasi steady-state experiments, and has an important reference to ensure the safe operation of the system. References C.D. Hu , Conceptual design of neutral beam injection system for EAST . Plasma Sci. Technol . 14 ( 6 ), 567 - 572 ( 2012 ). doi: 10.1088/1009-0630/14/6/03 http://doi.org/10.1088/1009-0630/14/6/03 Conceptual design of neutral beam injection system for EAST C.D. Hu , Y.J. Xu , Development progresses of EAST neutral beam injector . Nucl. Tech . 38 , 110603 ( 2015 ). doi: 10.11889/j.0253-3219.2015.hjs.38.110603 http://doi.org/10.11889/j.0253-3219.2015.hjs.38.110603 (in Chinese) Development progresses of EAST neutral beam injector C.D Hu , L.Z. Liang , Y.L. Xie et al ., Design of neutral beam-line of EAST . Plasma Sci. Technol . 13 ( 5 ), 541 - 558 ( 2011 ). doi: 10.1088/1009-0630/13/5/06 http://doi.org/10.1088/1009-0630/13/5/06 Design of neutral beam-line of EAST C.D. Hu , Preliminary results of ion beam extraction tests on EAST neutral beam injector . Plasma Sci. Technol . 14 ( 10 ), 871 - 873 ( 2012 ). doi: 10.1088/1009-0630/14/10/03 http://doi.org/10.1088/1009-0630/14/10/03 Preliminary results of ion beam extraction tests on EAST neutral beam injector H.S. Zhang , Ion source and high power neutral beam source . ( Atomic Energy Press , Beijing , 1999 ) (in Chinese) Ion source and high power neutral beam source G.J. Lei , S.F. Jiang , G.W. Zhong et al ., Ion source for HL-2A neutral beam injection . Chinese Phy. C . 32 ( s1 ), 271 - 273 ( 2008 ). Ion source for HL-2A neutral beam injection S. Pascal , 3D numerical simulations of hypervapotron cooling concept . Fusion Eng. Des . 82 ( 15 ), 1781 - 1785 ( 2007 ). doi: 10.1016/j.fusengdes.2006.12.011 http://doi.org/10.1016/j.fusengdes.2006.12.011 3D numerical simulations of hypervapotron cooling concept D.L. Youchison , J.H. Bullock , M.A. Ulrickson , Two-phase computational fluid dynamics analysis of a hypervapotron heatsink for ITER first wall applications . The 23rd IEEE/NPSS Symposium on Fusion Engineering , San Diego, California, USA , 1-5 June 2009 . doi: 10.1109/FUSION.2009.5226431 http://doi.org/10.1109/FUSION.2009.5226431 Two-phase computational fluid dynamics analysis of a hypervapotron heatsink for ITER first wall applications P.K. Domalapally , Computational thermal fluid dynamic analysis of cooling systems for fusion reactor components. Dissertation , Politecnico di Torino , 2013 Computational thermal fluid dynamic analysis of cooling systems for fusion reactor components. Dissertation R. Zanino , L.S. Richard , F. Subba et al ., CFD analysis of a regular sector of the ITER vacuum vessel. Part II: Thermal-hydraulic effects of the nuclear heat load . Fusion Eng. Des . 88 ( 12 ), 3248 - 3262 ( 2013 ). doi: 10.1016/j.fusengdes.2013.10.005 http://doi.org/10.1016/j.fusengdes.2013.10.005 CFD analysis of a regular sector of the ITER vacuum vessel. Part II: Thermal-hydraulic effects of the nuclear heat load L. Savoldi , R. Bonifetto , J. Izquierdo et al ., 3D thermal-hydraulic analysis of two irregular field joints for the ITER vacuum vessel . Fusion Eng. Des . 98-99 , 1605 - 1609 ( 2015 ). doi: 10.1016/j.fusengdes.2015.06.038 http://doi.org/10.1016/j.fusengdes.2015.06.038 3D thermal-hydraulic analysis of two irregular field joints for the ITER vacuum vessel X. Xiao , D.M. Yao , L. Cao et al ., Thermal hydraulic analysis of EAST W-divertor outer target . Nuclear Fusion and Plasma Physics . 35 ( 4 ), 356 - 360 ( 2015 ). doi: 10.16568/j.0254-6086.201504012 http://doi.org/10.16568/j.0254-6086.201504012 (in Chinese) Thermal hydraulic analysis of EAST W-divertor outer target L. Tao , C.D. Hu , Y.L. Xie et al ., Engineering design of ion dump for EAST nutral beam injection system . High Power Laser and Particle Beams . 25 ( 10 ), 2687 - 2692 ( 2013 ). doi: 10.3788/HPLPB20132510.2687 http://doi.org/10.3788/HPLPB20132510.2687 (in Chinese) Engineering design of ion dump for EAST nutral beam injection system L. Yu , C.D. Hu , S. Liu et al ., Water flow calorimetry system of EAST neutral beam injector . J. Fusion Energ . 32 ( 5 ), 547 - 551 ( 2013 ). doi: 10.1007/s10894-013-9613-1 http://doi.org/10.1007/s10894-013-9613-1 Water flow calorimetry system of EAST neutral beam injector Y.J. Xu , C.D. Hu , S. Liu et al ., Analysis of power deposition on heat load components for EAST neutral beam injector . J. Fusion Energ . 33 ( 6 ), 765 - 769 ( 2014 ). doi: 10.1007/s10894-014-9746-x http://doi.org/10.1007/s10894-014-9746-x Analysis of power deposition on heat load components for EAST neutral beam injector L. Tao , C.D. Hu , Y.L. Xie , Thermo-fluid-coupled analysis and simulation of calorimeter of Experimental Advanced Superconducting Tokamak neutral beam injection system on the thermal inertia principle . Adv. Mech. Eng . 9 ( 3 ), 1 - 9 ( 2017 ). doi: 10.1177/1687814017699093 http://doi.org/10.1177/1687814017699093 Thermo-fluid-coupled analysis and simulation of calorimeter of Experimental Advanced Superconducting Tokamak neutral beam injection system on the thermal inertia principle F.J. Wang , The principle and application of computational fluid dynamics software-CFD . ( Tsinghua University press , Beijing , 2004 ) (in Chinese) The principle and application of computational fluid dynamics software-CFD BF Inc . Fluent User’s Guide . ( Fluent Incorporated , New Hampshire Lebanon , 2010 ) Fluent User’s Guide Y. Yu , Tutorial of FLUENT introduction and advanced . ( Institute of Technology Press , Beijing , 2008 ) (in Chinese) Tutorial of FLUENT introduction and advanced ANSYS, Inc : ANSYS FLUENT Theory Guide (2015) . http://www.pdfdrive.net/ http://www.pdfdrive.net/ ANSYS FLUENT Theory Guide (2015) T.J. Xu . Thermal-hydraulic design, analysis and experiment research on EAST divertor. Dissertation , University of Chinese Academy of Sciences , 2013 ( in Chinese) Thermal-hydraulic design, analysis and experiment research on EAST divertor. Dissertation 10.1007/s41365-017-0349-x This work was supported by the Foundation of ASIPP (No. DSJJ-15-GC02) and the National Natural Science Foundation of China (No. 11605234). 2016-12-13 2017-04-12 2017-04-16 2017-12-21 2018-01-01 2021-04-11 © China Science Publishing & Media Ltd. (Science Press), Shanghai Institute of Applied Physics, the Chinese Academy of Sciences, ChineseNuclear Society and Springer Nature Singapore Pte Ltd. 2018 This is a post-peer-review, pre-copyedit version of an article published in Nuclear Science and Techniques. The final authenticated version is available online at: http://dx.doi.org/10.1007/s41365-017-0349-x http://dx.doi.org/10.1007/s41365-017-0349-x . 2018 Nuclear Science and Techniques 01 29