Research materials of construction of the fourth-generation nuclear reactors
Industrial networks supporting real time based on Ethernet importance of involving customers in the innovation process in relation to marketing innovation and marketing innovation retro shapes of display screen LCDs PI controller design method with Desired density table phase margin and settling time Trigonometric analysis coaxial stereoscopic camera system
This article focuses on the new generation of nuclear reactors developed in the framework of the international research program GEN IV. With innovative new-generation reactors must go even materials that are able to maintain a high standard density table properties, in accordance with the increased demands on the construction of nuclear power plants. In this work are described in more detail three different types of steel: austenitic steel NF 709, ferrite-martensitic density table steel EUROFER and a dispersion hardened steel ODS EUROFER. density table
The microstructure of these steels was investigated using positron annihilation spectroscopy. The results compared with known results of the measurement of impact strength (Charpy test), which were approximately the overall behavior of the individual materials.
Six concepts of new nuclear reactors were selected international research program GEN IV among others for further research density table and development. The main objectives of GEN IV include increased security, preventing diversion of nuclear fuel for weapons, radioactive waste and minimizing density table use of natural resources as well as reduce the cost of construction and operation of nuclear power plants.
The advantages of the new generation of JR compared to current nuclear sources are: significantly lower decay time of nuclear waste, streamline production (100-300 fold), and use of thorium fuel and MOX fuel in a closed fuel cycle [1]. High operating temperatures, radiation stress and subsequent changes in the mechanical properties of the components of these reactors, forcing scientists around the world explore and improve structural materials to withstand adverse effects with the least change in mechanical properties.
Austenite is a solid solution of carbon in iron. It is called the gamma-iron. Its crystals are light gray, soft, ductile density table and malleable. Not magnetic. Austenite has a face centered cubic structure. The carbon and low-alloy austenitic steels, austenite occurs only at high temperature (Fig. 1), only in certain high-alloy steel (nickel and manganese) and remains in the steel at room temperature. density table Austenitic chromium-nickel steel is the most widely used species of stainless material with excellent corrosion resistance, formability and weldability cold. It is characterized by resistance to water, steam, humidity, weak organic and inorganic acids.
NF709 material is produced by Nippon Steel (Tokyo, Japan). It is considered one of the best austenitic steels because of its resistance to creep and corrosion at high temperatures. The chemical composition density table of the material is shown in Table 1
Examination of the microstructure during aging at elevated temperatures is of paramount importance (Figure 2.). It is necessary to make sure that does not create any phase which promote creep, as well as the need to identify precipitation, which may not be created density table in the ordinary density table austenitic steel. NF709 composition is different from the other 20Cr/25Ni density table austenitic steels with its unique combination of carbon and nitrogen with niobium and titanium (Figure 3.).
Phase steel structure density table consists of ferrite matrix and martensite particles. Martensite content increases the strength of the base material and ferritic matrix provides a very good plastic properties. High chromium 9 to 12% FM steels are the best candidates for the production of components that have to withstand high temperatures up to 552 C. Just chromium concentration is a key parameter that provides the best corrosion resistance, resistance to the radiation volume density table increase and embrittlement. After crossing a certain percentage of chromium, however, no longer be prone to breaking. FM steels can be used as a structural density table material density table of reactor vessels and piping in the construction of an operating temperature density table of 450 C to 550 C.
FM steels are good candidates for the construction of components for supercritical water cooled reactor SCWR retesting due to their good properties of supercritical fossil power plants and the more benefits compared with austenitic corrosion resistant steels, such as: higher thermal conductivity, lower susceptibility to cracking due to corrosion and lower voltage bulking material after irradiation. However, they have limitations such as increased corrosion, low resistance to plastic flow of the material at high temperatures and irradiation embrittlement due to low temperature. [3, 4, 5].
Some FM steels after long-term placement in a radioactive environment are characterized by lower levels of activity. Such steels are called FM steels with a reduced degree of activation (activated reduce ferrite-martensite density table steel
Industrial networks supporting real time based on Ethernet importance of involving customers in the innovation process in relation to marketing innovation and marketing innovation retro shapes of display screen LCDs PI controller design method with Desired density table phase margin and settling time Trigonometric analysis coaxial stereoscopic camera system
This article focuses on the new generation of nuclear reactors developed in the framework of the international research program GEN IV. With innovative new-generation reactors must go even materials that are able to maintain a high standard density table properties, in accordance with the increased demands on the construction of nuclear power plants. In this work are described in more detail three different types of steel: austenitic steel NF 709, ferrite-martensitic density table steel EUROFER and a dispersion hardened steel ODS EUROFER. density table
The microstructure of these steels was investigated using positron annihilation spectroscopy. The results compared with known results of the measurement of impact strength (Charpy test), which were approximately the overall behavior of the individual materials.
Six concepts of new nuclear reactors were selected international research program GEN IV among others for further research density table and development. The main objectives of GEN IV include increased security, preventing diversion of nuclear fuel for weapons, radioactive waste and minimizing density table use of natural resources as well as reduce the cost of construction and operation of nuclear power plants.
The advantages of the new generation of JR compared to current nuclear sources are: significantly lower decay time of nuclear waste, streamline production (100-300 fold), and use of thorium fuel and MOX fuel in a closed fuel cycle [1]. High operating temperatures, radiation stress and subsequent changes in the mechanical properties of the components of these reactors, forcing scientists around the world explore and improve structural materials to withstand adverse effects with the least change in mechanical properties.
Austenite is a solid solution of carbon in iron. It is called the gamma-iron. Its crystals are light gray, soft, ductile density table and malleable. Not magnetic. Austenite has a face centered cubic structure. The carbon and low-alloy austenitic steels, austenite occurs only at high temperature (Fig. 1), only in certain high-alloy steel (nickel and manganese) and remains in the steel at room temperature. density table Austenitic chromium-nickel steel is the most widely used species of stainless material with excellent corrosion resistance, formability and weldability cold. It is characterized by resistance to water, steam, humidity, weak organic and inorganic acids.
NF709 material is produced by Nippon Steel (Tokyo, Japan). It is considered one of the best austenitic steels because of its resistance to creep and corrosion at high temperatures. The chemical composition density table of the material is shown in Table 1
Examination of the microstructure during aging at elevated temperatures is of paramount importance (Figure 2.). It is necessary to make sure that does not create any phase which promote creep, as well as the need to identify precipitation, which may not be created density table in the ordinary density table austenitic steel. NF709 composition is different from the other 20Cr/25Ni density table austenitic steels with its unique combination of carbon and nitrogen with niobium and titanium (Figure 3.).
Phase steel structure density table consists of ferrite matrix and martensite particles. Martensite content increases the strength of the base material and ferritic matrix provides a very good plastic properties. High chromium 9 to 12% FM steels are the best candidates for the production of components that have to withstand high temperatures up to 552 C. Just chromium concentration is a key parameter that provides the best corrosion resistance, resistance to the radiation volume density table increase and embrittlement. After crossing a certain percentage of chromium, however, no longer be prone to breaking. FM steels can be used as a structural density table material density table of reactor vessels and piping in the construction of an operating temperature density table of 450 C to 550 C.
FM steels are good candidates for the construction of components for supercritical water cooled reactor SCWR retesting due to their good properties of supercritical fossil power plants and the more benefits compared with austenitic corrosion resistant steels, such as: higher thermal conductivity, lower susceptibility to cracking due to corrosion and lower voltage bulking material after irradiation. However, they have limitations such as increased corrosion, low resistance to plastic flow of the material at high temperatures and irradiation embrittlement due to low temperature. [3, 4, 5].
Some FM steels after long-term placement in a radioactive environment are characterized by lower levels of activity. Such steels are called FM steels with a reduced degree of activation (activated reduce ferrite-martensite density table steel
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