Design optimization and fabrication method development for the HCCP TBM shield considering manufacturability

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-09-02 DOI:10.1016/j.fusengdes.2025.115409

Jae Sung Yoon , Suk-Kwon Kim , Seong Dae Park , Dong Won Lee , Hyoseong Gwon

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引用次数: 0

Abstract

The Helium Cooled Ceramic Pebble (HCCP) Test Blanket Module (TBM) is being co-designed in a Korean-EU collaboration. The HCCP TBM set consists of a TBM box and a TBM shield. This study aims to investigate the manufacturing process and propose a simplified manufacturing method to facilitate the fabrication of the HCCP TBM shield. The HCCP TBM shield structure comprises five blocks with piping connections consisting of water inlet/piping, helium inlet/piping, purge gas inlet/piping, and NAS I&C piping that run through these five blocks and connect to the TBM manifold. The existing Helium Cooled Pebble Bed (HCPB) TBM shield design includes multiple reinforcement plates, which pose challenge in welding and inspection. In this study, we proposed a simplified internal structure for the existing HCPB TBM shield, evaluated its structural soundness through thermal-hydraulic and thermo-mechanical analyses, and suggested a new fabrication method that reduces the number of reinforcement plates to improve fabrication convenience while maintaining the structural integrity of the existing design.

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考虑可制造性的HCCP TBM盾构设计优化与制造方法开发

韩欧合作开发的“氦冷陶瓷球（HCCP）测试毯模块（TBM）”。HCCP TBM机组由TBM箱体和TBM盾构组成。本研究旨在研究HCCP TBM盾构的制造工艺，并提出一种简化的制造方法，以方便HCCP TBM盾构的制造。HCCP TBM屏蔽结构包括5个管道连接块，包括进水/管道、氦气入口/管道、吹扫气体入口/管道，以及穿过这5个块并连接到TBM歧管的NAS I&；C管道。现有的氦气冷却球床（HCPB）掘进机盾构设计包括多个加固板，这给焊接和检测带来了挑战。在本研究中，我们对现有HCPB TBM盾构提出了一种简化的内部结构，通过热水力和热力学分析评估了其结构的可靠性，并提出了一种新的制造方法，减少了加固板的数量，提高了制造的便利性，同时保持了现有设计的结构完整性。

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来源期刊

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.