Integrity assessment of Tokamak-type fusion reactor First Wall and Blanket structures

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Mohammad Alabdullah , Nasr Ghoniem
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引用次数: 0

Abstract

This study presents a nonlinear structural analysis of the First Wall & Blanket (FW/B) of the Fusion Nuclear Science Facility (FNSF), aimed at identifying potential failure modes and estimating the component’s lifetime. The analysis focuses on the accumulation of plastic strain damage and applies fracture mechanics principles to assess the effects of radiation on mechanical properties. The study uses a database for reduced activation ferritic/martensitic steel F82H, with particular emphasis on radiation-induced changes in its mechanical properties. Safety factors for various failure modes are evaluated both at the beginning of life and after neutron irradiation under normal and off-normal operating conditions. The results indicate that the most critical failure modes are flow localization, thermal creep damage, and fast fracture due to radiation-induced reduction in fracture toughness. Based on current empirical prediction methods, we estimate that the FW/B structure will likely survive for approximately one year of operation under conditions of 1.2 MW/m2 neutron wall loading and 0.25 MW/m2 surface plasma thermal flux. These findings suggest that the effects of very high fluence (100–200 dpa) may be less significant than expected, with thermal creep damage and rapid fracture toughness degradation being the primary factors controlling failure. Therefore, there is a critical need to improve creep strength at temperatures above 500 °C and to mitigate fracture toughness degradation with increasing neutron fluence. Furthermore, the development of compact fusion energy sources with neutron wall loads greater than 5 MW/m2 may require new classes of structural materials to ensure their economic viability.
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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.
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