Vinit Shukla , Hitensinh Vaghela , Pratik Patel , Jotirmoy Das , Hyun-Sik Chang , Srinivasa Muralidhara , Cursan Marie , David Grillot
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The interdependency of the functional parameters of one component over the others needs to be assessed, as their integrated performance under the dynamic heat load deposition from the SC magnets may impact the overall operation of the ITER cryogenic system. The ACBs are equipped with two helium baths having ∼ 1200 kg of He inventory and situated inside the Tokamak building. These baths act as a thermal buffer for the LHe plant, situated in the cryoplant building, allowing it to operate at a quasi-steady state despite heat load variation from the applications. Such a large helium inventory can challenge the secondary confinement system of ITER due to helium ingress accidental events and thus needs to be optimized. The integrated system-level simulation is therefore necessary for the safe and reliable operation of the cryogenic system under such demanding requirements. The present study summarizes the results obtained for ACBs dedicated to the magnet system, including CTCB for the enhanced ITER operation modes, and confirms the integrated performance of the system. The results show that the LHe baths inside the ACBs can be used as a thermal buffer with the proposed limit of initial filling and by keeping a constant opening of the respective J-T valves upstream of the LHe baths. 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引用次数: 0
摘要
热核实验堆低温系统由液氦(LHe)装置、低温配送(CD)系统和低温管线组成。专用于冷却超导(SC)磁体系统的辅助冷箱(ACB)和 ITER CD 系统的低温终端冷箱(CTCB)正处于工厂验收阶段。ACB 的内部组件(低温阀、冷压缩机 (CCp)、热交换器和冷循环器 (CCr))已确定尺寸并组装完毕,以确保其功能性。需要对一个组件的功能参数与其他组件的相互依存关系进行评估,因为它们在 SC 磁体动态热负荷沉积下的综合性能可能会影响热核实验堆低温系统的整体运行。ACB 配备了两个氦浴,氦存量为 1200 千克,位于托卡马克建筑内。这些氦池为低温装置大楼内的低温氦设备提供热缓冲,使其能够在应用产生热负荷变化的情况下仍能以准稳定状态运行。如此庞大的氦库存可能会因氦气意外进入而对热核实验堆的二次约束系统造成挑战,因此需要对其进行优化。因此,为了使低温系统在如此苛刻的要求下安全可靠地运行,有必要进行综合系统级模拟。本研究总结了磁体系统专用 ACB(包括用于增强型热核实验堆运行模式的 CTCB)的结果,并确认了系统的综合性能。研究结果表明,ACB 内部的氦气槽可用作热缓冲器,建议限制初始填充量,并保持氦气槽上游相应 J-T 阀门的恒定开度。研究结果和提出的建议将有助于减轻氦气厂的脉冲热负荷,同时最大限度地减少氦气库存。
Dynamic simulation of ITER cryo-distribution system using Aspen HYSYS
The ITER cryogenic system consists of the Liquid Helium (LHe) plant, the Cryo-Distribution (CD) system, and the cryo-lines. The Auxiliary Cold Boxes (ACBs) dedicated to cooling the superconducting (SC) magnet system and the Cryoplant Termination Cold Box (CTCB) of the ITER CD system are in the factory acceptance phase. The internal components of ACBs, e.g., cryogenic valves, a cold compressor (CCp), heat exchangers, and a cold circulator (CCr), have been sized and assembled, ensuring their functionality. The interdependency of the functional parameters of one component over the others needs to be assessed, as their integrated performance under the dynamic heat load deposition from the SC magnets may impact the overall operation of the ITER cryogenic system. The ACBs are equipped with two helium baths having ∼ 1200 kg of He inventory and situated inside the Tokamak building. These baths act as a thermal buffer for the LHe plant, situated in the cryoplant building, allowing it to operate at a quasi-steady state despite heat load variation from the applications. Such a large helium inventory can challenge the secondary confinement system of ITER due to helium ingress accidental events and thus needs to be optimized. The integrated system-level simulation is therefore necessary for the safe and reliable operation of the cryogenic system under such demanding requirements. The present study summarizes the results obtained for ACBs dedicated to the magnet system, including CTCB for the enhanced ITER operation modes, and confirms the integrated performance of the system. The results show that the LHe baths inside the ACBs can be used as a thermal buffer with the proposed limit of initial filling and by keeping a constant opening of the respective J-T valves upstream of the LHe baths. The study outcome and the proposed recommendations would be beneficial to mitigate the pulsed heat load to the LHe plant while minimizing the helium inventory.
期刊介绍:
The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.