Innovative RAFM steels with improved impact properties

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Carlo Cristalli , Luciano Bozzetto , Alessandro Colaneri , Roberto Sorci , Oriana Tassa
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引用次数: 0

Abstract

The contribution of ENEA together with Rina-CSM to the Eurofusion programme “WPMAT" (Work Package MATerials) deals with the development of innovative RAFM steels able to withstand the critical low temperature (280–300 °C in the “water-cooling” option) foreseen for the blanket of the first DEMO reactor. Therefore the target is the development of tougher alloys, suitable to prevent the low temperature irradiation embrittlement. In addition to the DBTT shift due to the dpa damage under irradiation, also the issue of the increased embrittlement due to Helium production must be taken into account.
The alloy design focused on chemical composition optimization in terms of contents of some main key elements as Carbon, Manganese, Vanadium, Nitrogen and Tantalum. An overall indication deriving from the last neutron irradiation experiment was to increase Vanadium and Nitrogen at the expense of Carbon and Manganese. The ingot has then been cast with accurate control of impurities. The final product has proven compliant to the specifications concerning RAFM steels for fusion environment.
Alternative thermo-mechanical treatments have then been applied on this RAFM steel. On the one hand the DBTT after a standard double normalization and tempering treatment is definitely successful; -140 °C on KLST specimens. The extremely low DBTT must be considered a consequence of the choices done on the chemical composition. On the other hand a particular TMT, whose aim is to induce recrystallization of the laths substructure and obtain an equiaxed nano-grain structure, has been investigated. Supposed to increase the resistance to crack propagation, the decrease in grain size (less than one μm) leads to a transition curve that doesn't show a sharp drop in the absorbed energy, but instead a more gradual transition from the USE to the LSE. The tensile properties in the recrystallized condition result markedly higher than after the conventional treatment.
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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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