Laves phases with their comparably simple crystal structure are very common intermetallic phases and can be formed from element combinations all over the periodic table resulting in a huge number of known examples. Even though this type of phases is known for almost 100 years, and although a lot of information on stability, structure, and properties has accumulated especially during the last about 20 years, systematic evaluation and rationalization of this information in particular as a function of the involved elements is often lacking. It is one of the two main goals of this review to summarize the knowledge for some selected respective topics with a certain focus on non-stoichiometric, i.e., non-ideal Laves phases. The second, central goal of the review is to give a systematic overview about the role of Laves phases in all kinds of materials for functional and structural applications. There is a surprisingly broad range of successful utilization of Laves phases in functional applications comprising Laves phases as hydrogen storage material (Hydraloy), as magneto-mechanical sensors and actuators (Terfenol), or for wear- and corrosion-resistant coatings in corrosive atmospheres and at high temperatures (Tribaloy), to name but a few. Regarding structural applications, there is a renewed interest in using Laves phases for creep-strengthening of high-temperature steels and new respective alloy design concepts were developed and successfully tested. Apart from steels, Laves phases also occur in various other kinds of structural materials sometimes effectively improving properties, but often also acting in a detrimental way.

/pdf/laves-phases-a-review-of-their-functional-and-structural-1r0nnkeily.pdf

Laves phases: a review of their functional and structural applications and an improved fundamental understanding of stability and properties

A program for China low activation martensitic steel (CLAM) development has been underway since 2001 to satisfy the material requirements of the test blanket module (TBM) for ITER, China fusion engineering test reactor and China fusion demonstration reactor It has been undertaken by the Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences under wide domestic and international collaborations Extensive work and efforts are being devoted to the R&D of CLAM, such as mechanical property evaluation before and after neutron irradiation, fabrication of scaled TBM by welding and additive manufacturing, improvement of its irradiation resistance as well as high temperature properties by precipitate strengthening to achieve its final successful application in fusion systems The status and improvement of CLAM are introduced in this paper

https://iopscience.iop.org/article/10.1088/1741-4326/aa763f/pdf

Status and improvement of CLAM for nuclear application

A high-entropy V35Ti35Fe15Cr10Zr5 alloy with excellent high-temperature strength

Effects of Ti and Ta addition on microstructure stability and tensile properties of reduced activation ferritic/martensitic steel for nuclear fusion reactors

Evolution of microstructure and mechanical properties of 9Cr ferrite/martensite steels with different Si content after long-term aging at 550 °C

Effect of Thermal Aging on Microstructure and Mechanical Properties of China Low-Activation Martensitic Steel at 550 °C

The invention provides martensitic steel. The martensitic steel mainly comprises, by weight, 8.0-8.8% of Cr, 1.3-1.7% of W, 0.15-0.25% of V, 0.15-0.25% of Ta, 0.30-0.70% of Mn, 0.06-0.10% of C, 0.02-0.06% of N and 0.005-0.015% of Zr. According to the martensitic steel, the content of the Cr is reduced and the N element is added to replace the C element partially, so that the precipitated amount of M C is reduced in the processing process of materials; the composition proportion of the forming elements of an MX phase is controlled strictly to ensure that the Ta and the V are precipitated in the form of the MX phase to a most extent; and meanwhile, a special heat treatment technology is adopted to obtain tiny MX phase which are distributed in a dispersion mode, and therefore the high-temperature behavior of the materials in the service process is enhanced effectively.

Novel dispersion-strengthened low-activation radiation-resistant martensitic steel and heat treatment technology thereof

The invention discloses a heat mechanical treatment method for improving the low activation martensite steel mechanical property. On the basis of an existing low activation martensite steel board preparing technology, a method combining rapid water cooling treatment after secondary hot rolling machining and high-temperature tempering treatment is adopted, and a low activation martensite steel board with the more excellent performance is obtained. Through the method, the yield strength of the low activation martensite steel board is increased to above 650 MPa from original 530 MPa, the tensile strength is improved to above 830 MPa from original 660 MPa, and meanwhile, toughness can meet the use requirement of a fusion reactor.

Heat mechanical treatment method for improving low activation martensite steel mechanical property

The invention relates to low-activity martensitic steel with high-temperature mechanical performance and a heat treatment process. The low-activity martensitic steel comprises main components of 8.5-9.5% of Cr, 1.2-1.7% of W, 0.15-0.25% of V, 0.12-0.18% of Ta, 0.4-0.5% of Mn, (C+N) not more than 0.17% and not less than 0.09%, N less than 0.07% (wt.%), and the balance of Fe elements; and the purpose of controlling C and N is to form fine dispersed carbonitride in subsequent treatment to enhance the material high-temperature performance. Low-activity martensitic steel plates molded by rolling are heated to 1100+/-50 DEG C, are insulated by 40-120 min according to different thicknesses and sizes to discharge from a furnace, are quickly cooled by water to reach the room temperature, are reheated to 740+/-20 DEG C, are insulated by 90-140 min according to different thicknesses and sizes to discharge from the furnace, and are cooled by air to reach the room temperature. The high-temperature strength and the high-temperature durability of radiation-resistance low-activity steel are prominently improved to lay the foundation to the use temperature of the radiation-resistance low-activity steel.

Low-activity martensitic steel with high-temperature mechanical performance and heat treatment process

The invention discloses low-activation bainitic steel applicable to a neutron-irradiated environment and a preparation method thereof. A structural steel material has a matrix element of an element Fe, contains 2.5 to 3.5 percent (by weight) of Cr, 2.2 to 2.8 percent (by weight) of W, 0.2 to 0.25 percent (by weight) of V, 0.12 to 0.18 percent (by weight) of Ta, 0.40 to 0.80 percent (by weight) of Mn, 0.40 to 0.45 percent (by weight) of Si, 0.08 to 0.12 percent (by weight) of C and 0.01 to 0.05 percent (by weight) of N, and is suitably used in a fusion-reactor environment. Radioactive nuclides Mo, Ni, Cu, Nb and the like, which can be enabled to have long service life after being subjected to neutron irradiation, are strictly controlled in the componential formula of the steel, so as to guarantee that the low-activation bainitic steel applicable to the neutron-irradiated environment has a low-activation characteristic. A bainitic structural steel material has a favorable high-temperature property, particularly has a high-temperature croop property, can need no heat treatment after being welded, and is suitable for making large-sized components of a fusion-reactor vacuum container and the like.

Low-activation bainitic steel applicable to neutron-irradiated environment and preparation method thereof

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