为热核实验堆紫外线光谱仪系统开发双层波纹管

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2024-08-24 DOI:10.1016/j.fusengdes.2024.114643
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引用次数: 0

摘要

本研究介绍了用于热核实验堆真空紫外(VUV)光谱仪系统的双壁波纹管的设计和开发。设计这些波纹管是为了适应热核实验堆真空容器的热膨胀和其他接口负载导致的端口塞位移。正在开发的三个真空紫外光谱仪系统--真空紫外核心测量光谱仪、分流器-真空紫外光谱仪和真空紫外边缘光谱仪--旨在测量真空紫外光谱,以监测等离子体中的杂质种类。虽然位于间隙和端口单元区域的热核实验堆紫外分光计的舱外组件固定在托卡马克建筑上,但由于真空容器的热膨胀,与视线管相连的端口塞封闭板预计会在垂直和径向上移动几厘米。因此,要保证系统的结构完整性,就需要一种能够补偿热膨胀引起的位移的柔性结构。为满足这一需求,我们开发了两种类型的双壁波纹管,即用于横向位移的万向节波纹管和用于轴向位移的轴向波纹管。这些波纹管是根据 ASME SEC.VIII 规范和 EJMA 标准开发的,以满足热核实验堆的安全和真空要求。由于真空波纹管在真空安全方面的脆弱性,真空波纹管必须采用双层壁。通过对制造的原型进行功能测试,确认了所设计波纹管的结构完整性和功能性。
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Development of double-walled bellows for ITER VUV spectrometer systems

This study describes the design and development of double-walled bellows used in ITER's vacuum ultra-violet (VUV) spectrometer systems. These bellows were designed to accommodate port plug displacement resulting from the thermal expansion of the ITER vacuum vessel and other interface loads. The three VUV spectrometer systems under development—the VUV core survey spectrometer, divertor-VUV spectrometer, and VUV-edge spectrometer—are intended to measure the VUV spectrum to monitor impurity species in the plasma. While the ex-vessel components of ITER VUV spectrometers in the interspace and port cell areas, are fixed to the tokamak building, the closure plate of the port plugs, to which the sight pipes are attached, is expected to move by several centimeters both vertically and radially owing to the vacuum vessel's thermal expansion. As a result, the structural integrity of the system requires a flexible structure that can compensate for displacement caused by thermal expansion. To address this need, two types of double-walled bellows were developed, gimbal bellows for lateral displacement and axial bellows for axial displacement. These were developed in accordance with the ASME SEC.VIII code and EJMA standard to meet ITER's safety and vacuum requirements. A double wall is mandated for vacuum bellows due to their vulnerability in terms of vacuum safety. The structural integrity and functionality of the designed bellows were confirmed through functional tests on the manufactured prototype.

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来源期刊
Fusion Engineering and Design
Fusion Engineering and Design 工程技术-核科学技术
CiteScore
3.50
自引率
23.50%
发文量
275
审稿时长
3.8 months
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.
期刊最新文献
On the fabrication of ultrafine-grained potassium-doped tungsten: Mechanical milling and spark plasma sintering of K-doped W powder prepared by evaporation-condensation method X-ray imaging crystal spectrometer (XICS) diagnostic on the HL-3 tokamak The energy output equilibrium scheme with intermediate energy storage for tokamak fusion power plant Measurement of the mechanical vibration and its impact on the magnetic diagnostics in the J-TEXT tokamak Overview of the TCV digital real-time plasma control system and its applications
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