Effects of interlayer on fracture and fatigue crack resisting of double-wall tubes in WCCB

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

Fusion Engineering and Design Pub Date : 2025-09-19 DOI:10.1016/j.fusengdes.2025.115450

Wanjing Wang , Lingming Huang , Jichao Wang , Zhenjie Zhang , Qun Li , Zhenmao Chen , Peisong Du , Haishan Zhou , Guang-Nan Luo

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引用次数: 0

Abstract

The double wall tubes (DWT) in the tritium breeding zone play a critical role in the Water Coolant Ceramics Blanket (WCCB) of the China Fusion Engineering Testing Reactor (CFETR). In order to assess the effectiveness of DWT in resisting type-I crack propagation, a sandwich structure plate consisting of steel-interlayer-steel was fabricated using heat isostatic press (HIP) technology. Subsequently, experimental investigations were carried out to study fatigue crack propagation under three-point bending conditions. The results demonstrate that continuous fatigue bending leads to the generation of a type-I crack perpendicular to the interface; however, there is stagnation at the interface before expanding sideways to form a type-II crack. Furthermore, it was observed that specimens with Ni interlayers exhibit more effective resistance against type-II crack extension compared to those with Cu interlayers. In the discussion, a J-integral-based fatigue crack propagation model was proposed, which can accurately predict the deflection behavior of cracks in multilayer structures with interfaces. This study indicates that the DWT could effectively prevent the propagation of type-I cracks.

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夹层对WCCB双壁管断裂和抗疲劳裂纹性能的影响

氚增殖区的双壁管（DWT）在中国核聚变工程试验堆（CFETR）水冷剂陶瓷包层（WCCB）中起着至关重要的作用。为了评估DWT抗i型裂纹扩展的有效性，采用热等静压（HIP）技术制作了由钢-层间钢组成的夹层结构板。随后，进行了三点弯曲条件下疲劳裂纹扩展的实验研究。结果表明：连续疲劳弯曲导致垂直于界面的i型裂纹的产生；然而，在横向扩展形成ii型裂纹之前，界面处存在滞止。此外，与Cu夹层相比，Ni夹层对ii型裂纹扩展表现出更有效的抵抗能力。在讨论中，提出了一种基于j积分的疲劳裂纹扩展模型，该模型可以准确地预测具有界面的多层结构中裂纹的挠曲行为。研究表明，DWT可以有效地阻止i型裂纹的扩展。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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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.