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Fusion engineering and design
North-Holland
Fusion engineering and design

North-Holland

半月刊

0920-3796

Fusion engineering and design/Journal Fusion engineering and designSCIEI
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    A structural optimized method and verification of fusion converter for high current sharing performance

    Wang, ZhongmaShao, XingxingWu, JiamengXu, Tao...
    1.1-1.11页
    查看更多>>摘要：Current unbalance caused by impedance disparities among multiple parallel branches can lead to accelerated aging of some power devices and localized overheating, posing a threat to the normal operation of fusion power supplies. A method for improving the current sharing performance of fusion converters with paralleled branches based on structural parameter optimization is proposed in this paper. Firstly, a high-precision converter bridge arm structure is constructed using ANSYS Q3D, and sub-circuits of segmented modules are extracted; subsequently, a circuit model is built in Simplorer, and the current of each branch is obtained through joint simulation with Simplorer; then, with branch current as the matching parameter, an adaptive target optimization algorithm is utilized to iterate and optimize structural parameters, thereby acquiring a set of bridge arm structures with optimal current sharing performance; finally, fine-tuning is conducted considering the actual spatial limitation. To validate the superiority of the proposed method, the current sharing effects of the structures before and after optimization under both steady-state and short-circuit conditions are analyzed and compared. The results indicate that the optimized structure has shown significant improvements in terms of current sharing coefficient, over-current ratio, and maximum turn-off error time. This method could be used for the current sharing design of fusion power supplies and related multiple parallel devices.
      原文链接:
    • NETL
    • NSTL
    • Elsevier

    Corrosion behavior of 9Cr-RAFM steel in liquid lithium and lead-lithium at 550°C for 500 h

    Zhang, D. H.Meng, X. C.Zuo, G. Z.Li, X....
    1.1-1.9页
    查看更多>>摘要：Liquid lithium (Li) and liquid lead-lithium (LiPb) are candidate coolant/breeders in fusion reactor blankets. RAFM is an advanced structural material with many advantages and has attracted much attention for application in fusion liquid blankets. Thus, the compatibility of the RAFM steel with liquid metals plays an important role in liquid metal blankets. In this study, we investigated the corrosion behavior of China 9Cr-RAFM steel in static liquid Li and LiPb at 550 degrees C for 500 h. The results show that the corrosion of this steel in liquid LiPb is more serious than that in liquid Li. The mass loss rates of the samples in liquid Li and LiPb were 0.528 and 1.92 g/ (m2 & sdot;h), respectively. After exposed to liquid Li and LiPb, the samples exhibited mass loss, grain boundary corrosion and pitting corrosion due to physical dissolution and chemical reactions. And the corrosion of liquid Li and LiPb did not affect the Vickers hardness of the sample.
      原文链接:
    • NETL
    • NSTL
    • Elsevier

    Observation of greater blister skin thickness compared with the implantation depth of high-energy helium in tungsten

    Uchida, YukiSaito, SeikiSuzuki, TsuneoTakahashi, Kazumasa...
    1.1-1.8页
    查看更多>>摘要：Blistering of pure tungsten by MeV helium (He) bombardment was investigated by examination of the thickness of the blister skin. Polycrystalline tungsten (W) was fabricated by powder metallurgy and irradiated with, 4 MeV He2+, of fluence 1018 ions cm- 2, and a flux of 7 x 1013 ions cm- 2s- 1 at 332 K. We observed that the thickness of the blister skin was greater than anticipated with respect to the peak in the amount of He in W following focused ion beam (FIB) and a scanning electron microscopy (SEM) examination. He bubbles were observed at the position of the crack with transmission electron microscopy (TEM). Yield stress vs displacement per atom (DPA) was calculated. The stress increaseed from the surface to the maximum penetration depth and was shown to reach a minimum at a deeper position than the peak in the amount of implanted He.
      原文链接:
    • NETL
    • NSTL
    • Elsevier

    Thermal-hydraulic analysis of the ITER CCWS-1 cooling loop

    Agnello, GiuseppeCiampichetti, AndreaDell'Orco, GiovanniDi Maio, Pietro Alessandro...
    1.1-1.15页
    查看更多>>摘要：ITER is designed to produce heat power from the deuterium-tritium fusion reaction burning the confined plasma inside the vacuum vessel. The effective removal of the power generated from fusion reactions and auxiliary systems (e.g. plasma heating systems, cryogenic systems, coils, etc.) represents a key point for the success of ITER. CCWS-1 is a pressurized cooling loop with the main function to guarantee cooling water to TCWS and other served auxiliary systems (e.g. vacuum pumps) maintaining temperature, pressure, flow rates and water chemistry within prescribed values. To support the CCWS-1 design and verify the requirements at the clients' interface during the different operational modes of the machine, a thermal-hydraulic campaign has been carried out. The work has been conducted using the commercially available thermal-hydraulic software AFT Fathom, performing steady-state and heat transfer analyses of complex systems. The present paper summarizes the computational models, and the hypotheses and critically discusses the obtained outcomes.
      原文链接:
    • NETL
    • NSTL
    • Elsevier

    Thermal hydraulic analysis on the heat transfer enhancement of the COOL blanket first wall for CFETR

    Feng, WeiJiang, KechengChen, LeiLiu, Songlin...
    1.1-1.13页
    查看更多>>摘要：The supercritical CO2 cOoled Lithium-Lead (COOL) blanket is one of the advanced candidate blankets for China Fusion Engineering Test Reactor (CFETR). In this blanket, the first wall (FW) is subjected to high heat flux from plasma and the nuclear heat produced by the interaction between the blanket materials and neutrons. To ensure that the FW has superior heat removal capability and that the material temperature remains below the allowable limit. First of all, this paper conducts the thermal- hydraulic optimization in view of the hydraulic diameter and pitch to achieve a better smooth channel design. Then, the effects of two heat transfer enhancement techniques, i. e. artificial roughness and placement of ribs (both set on the wall close to the plasma side of the front wall), on the maximum temperature of the FW are analyzed. Considering both pressure drop and heat transfer, the enhanced heat transfer performance is evaluated using PEC. The results show that setting a roughness of 0.045 mm at the fillet and coupling V-shaped ribs with the distance of 25 mm and an angle of 60 degrees on the front wall can reduce the maximum temperature of FW from the original 551 degrees C to 508 degrees C, achieve a convective heat transfer coefficient (HTC) of 9290 W/(K & sdot;m2), and attain PEC of 1.85. Finally, stress evaluation of this design is performed using ANSYS Mechanical, and the results meet the design specification standards.
      原文链接:
    • NETL
    • NSTL
    • Elsevier

    Helium impurity measurement in hydrogen isotope mixtures by gas chromatography

    Li, XiaofengXia, TifengLei, Qianghua
    1.1-1.6页
    查看更多>>摘要：Traditional gas chromatography (GC) often encounters the challenge in accurately detecting helium content in hydrogen isotope gases due to interference from hydrogen isotopes. To address this issue, a novel method utilizing a pre-treatment column (PC) filled with Pd/Al2O3 particles to eliminate hydrogen isotopes has been proposed. Experimental results show that the PC can completely adsorb hydrogen isotopes, leading to the disappearance of hydrogen isotope peak in the chromatogram. After the equipment of PC, the detection limit of helium is below 2 ppm at a sampling pressure of 100 kPa. Compared to the original measurement method, the PC-equipped GC reduces the measurement uncertainty of helium by 1 to 2 orders of magnitude. Moreover, the equipment of PC does not hinder the daily operation and maintenance of GC, and the PC can be consecutively used for over 20 runs.
      原文链接:
    • NETL
    • NSTL
    • Elsevier

    Thermal behavior of the KSTAR tungsten cassette divertor in KSTAR 2023 campaign

    Kim, Koung MoonAhn, Hee-JaeKim, Young OkKim, Hyunseok...
    1.1-1.9页
    查看更多>>摘要：The thermal behavior of the KSTAR Plasma-Facing Components (PFCs), with a focus on the newly installed Tungsten Cassette Divertor (TCD), was analyzed based on the results of the KSTAR 2023 campaign. Prior to the plasma experiment, an in-situ active cooling experiment was conducted to measure the flow rate of the Baking and Cooling pipelines (B&C lines) in each port, as such measurements cannot be performed during the plasma experiment. The flow rate supplied to the TCD was estimated from the in-situ experiment results and applied as the supply flow rate for subsequent Computational Fluid Dynamics (CFD) analysis. The study examined the results of the 1st baking operation, conducted to enhance the vacuum conditions; the 102-second long-pulse plasma experiment achieved in 2023; and the 2nd baking operation, performed to remove residual moisture from the B&C lines after the plasma experiment. Thermal margins were evaluated using CFD simulations for a single TCD under steady-state conditions. Additionally, to evaluate thermal performance under conservative conditions, a pump failure scenario was analyzed, confirming that temperatures remained within the design limits. The findings confirmed that sufficient thermal margin, defined by the design temperature limits of the tungsten and CuCrZr pipes, was secured during the 102-second long-pulse plasma experiment, despite minor variations in flow rates among the TCD B&C ports and the eight TCDs within the same port. In conclusion, the TCD effectively dissipates plasma heat loads under steady-state conditions comparable to those of this long-pulse experiment.
      原文链接:
    • NETL
    • NSTL
    • Elsevier

    Thermal-mechanical analysis and optimization on the critical components of the high temperature PbLi loop for CFETR

    Yu, YueJiang, KechengChen, LeiLiu, Songlin...
    1.1-1.20页
    查看更多>>摘要：In the support of Comprehensive Research Facility for Fusion Technology (CRAFT) Program of China, the high temperature PbLi loop is under development, which will be employed to experimentally study the MagnetoHydroDynamics (MHD) effects for the supercritical carbon dioxide (s-CO2) cOoled Lithium-Lead (COOL) blanket. In the current design, the temperature of PbLi is operating in the range of 300 degrees C-700 degrees C, and the material for components is carefully selected in view of the baseline 550 degrees C. When the temperature is higher than this value, the nickel-based alloy that can resist high temperature is adopted. Otherwise, the stainless steel 316 is used. In this loop, there are two components that are considered as the most critical and fragile due to the highest operating temperature up to 700 degrees C, including the main heater and primary mixer. Therefore, the thermalmechanical analysis and optimization on these two critical components are performed in this paper, and the stress results are evaluated according to the relevant standards. For the main heater, both the PbLi outlet temperature and the structural temperature meet the requirements under the maximum operating condition. Although the stress in some regions exceeds the allowable limits, it can be solved during the manufacturing process. For the primary mixer, the optimization is performed from three aspects, i.e. structural design, structural material, and increasing cold PbLi temperature. The results indicate that one of the designs exhibits better stress performance. Tungsten shows satisfying mechanical properties, but there are challenges in machining. While N06625 can only meet the stress criteria of the external components. The thermal stress is decreased with the reduction of the temperature difference between the hot and cold PbLi. Furthermore, the mixing performance is effectively enhanced by extending the length of the helical and the outlet nozzle. The results can provide data support for the processing and manufacturing of these two critical components to ensure the safe operation of the PbLi loop.
      原文链接:
    • NETL
    • NSTL
    • Elsevier

    Physics and technology maturity level required for the K-DEMO design points

    Kang, J. S.Jo, G.Kwon, J-m.Hong, B. G....
    1.1-1.9页
    查看更多>>摘要：The conceptual design study for the Korean fusion demonstration reactor (K-DEMO) has been conducted, placing an emphasis on the imperative to reduce the reactor's dimension as a means to cost minimization. The design space of K-DEMO was delineated based on maturity level of physics and technology. Advanced technology features such as a use of a tungsten carbide (WC) shield, a tritium breeding blanket concept of He cooled lithium lead (HCLL), the maximum allowable magnetic field at the TF coil, B-max = 16 T with a Nb3Sn superconducting material, etc. were adopted. With specified design criteria, including a net electric power >= 300 MW, a fusion gain, Q > 20.0, a neutron wall loading < 2.0 MW/m(2), an indicator of divertor power handling capability (ratio of power to divertor to major radius), P-div/R-0 < 25 MW/m, and the capability for steady-state operation, a design space of the K-DEMO was established based on the energy confinement scaling law of IPB98[y,2] under physics level of Greenwald density fraction, n(e)/n(G) < 1.2, normalized plasma beta (ratio of plasma pressure to magnetic pressure normalized by plasma current divided by the product of minor radius and toroidal magnetic field), beta(N) < 3.0, confinement enhancement factor, H < 1.3, and a direct cost <= 7.5 B$. After an exploration of system parameters, prospective design points for K-DEMO were identified, characterized by a major radius, R-0 similar to 6.8 m, an aspect ratio, A = 3.1, a toroidal magnetic field at plasma center, B-T >= 6.5 T, and a fusion power, P-fusion similar to 1,500 MW. When beta-independent energy confinement scaling law was applied, the design points were accessible with smaller n(e)/n(G), beta(N), H, P-fusion, and larger B-T. From a sensitivity analysis of the minimum major radius to the input parameters, strong sensitivities to Greenwald density fraction, n(e)/n(G), normalized plasma beta, beta(N), confinement enhancement factor, H, edge safety factor, q(edge), and elongation, kappa were found. Additionally, the operational envelope in physics and technology parameters was established with system parameters associated with the design points.
      原文链接:
    • NETL
    • NSTL
    • Elsevier

    Implementation of high-speed data acquisition at DIII-D

    Keller, A.Piglowski, D.Penaflor, B. G.
    1.1-1.4页
    查看更多>>摘要：Research at the DIII-D National Fusion Facility in San Diego focuses on short pulse plasma discharges that specialize on various shaping profiles. High-speed data collection is a critical component for the operation of many of DIII-D's diagnostics and is fundamental for capturing high-resolution data used in experimental data analysis. Differing techniques enable the plasma control system (PCS) to perform complex real-time feedback control on microsecond time scales. This work presents a comprehensive overview of data acquisition, focusing on the hardware and software used in reliable data acquisition at DIII-D. The robust nature of the data acquisition system allows for various techniques to coexist seamlessly. However, as modern systems capable of nanosecond resolution become more common, existing architectures will need to be modified. By addressing the key challenges of high-speed data acquisition, DIII-D is able to provide real-time data used in plasma operation and has the ability to acquire high fidelity data needed for future experimental fusion reactors, such as ITER.
      原文链接:
    • NETL
    • NSTL
    • Elsevier