What is a fast neutron breeder reactor?
The fast breeder reactor was a type of fission chain reactor. In this type of reactor, neutrons were used to cause fission. The fuel regeneration speed was higher than the consumption speed, so it could proliferate quickly. Therefore, it was also called a fast-breeding reactor. Among them, the fast neutrons emitted by the fission reaction of Pu- 239 could be absorbed by Uranium- 238 in the peripheral regeneration zone and become Uranium- 239. Uranium- 239 was converted into Pu- 239 after several decays, which could continue to be used for fission after purification. In a large fast reactor, on average, every 10 uranium- 235 nuclei could be converted into 12 to 14 uranium- 238 into Pu- 239. The "fast" in fast reactors referred to the faster speed of neutrons. It could use uranium- 238, which was difficult to use in thermal neutrons. After absorbing neutrons, Uranium- 238 became compound Uranium- 239. After two beta decays, it was converted into the fissible nuclear fuel Plutonium- 239. The fast reactor technology formed a closed cycle, constantly producing new fuel during operation, achieving the goal of burning more nuclear fuel, which could increase the utilization rate of uranium resources to at least 60%. This meant that depleted uranium, low-grade uranium ore, and even uranium in seawater could be used as fuel sources. It could also minimize the accumulation of uranium- 238 in traditional nuclear power plants and minimize the discharge of radioactive materials. The international community generally believed that the development and promotion of fast reactor technology could fundamentally solve the problem of global energy sustainable development and green development. Some of the fast neutron breeder reactors used liquid metal as a cooling agent, known as the sodium-cooled fast neutron reactor. This was also the mainstream of the current fast neutron breeder reactor. It had been built in many countries and was one of the fourth-generation reactors under research. Read more exciting novels for free
Fast breeder reactor
The English translation of the fast neutron breeder reactor was "fast breeder reactor", which could also be translated as "fast neutron breeder reactor". <a href="/?from=ask_words" style="color:red" target="_blank">Read more exciting novels for free</a>
Neutron reactor
A neutron reactor could be a Neutron reactor. <a href="/?from=ask_words" style="color:red" target="_blank">Read more exciting novels for free</a>
reactor neutron cross section
The neutron cross section included the microscopic cross section and the microscopic cross section. Microscopic Section: - The product of the microscopic cross section and the density of the target nucleus beam was defined as the microscopic cross section. The microscopic cross-section symbol was a, which was related to the nature of the target nucleus and the neutron energy. It could be calculated by the formula: a = -I/(I·N x), where-I/I was the fraction of neutrons that interacted with the target nucleus by the parallel neutron beam, and N x was the number of target nuclei per unit area. The cross-sections of different nuclear reactions were represented by different annotations. For example, s,e,in, r,f,a, and t represented the scattering, elastic scattering, inelastic scattering, radiation capture, fission, absorption, and total reaction cross-sections of the interaction between the neutron and the nucleus. Here, a represented the absorption cross-section. The absorption cross-section was a measure of the probability of the absorption process. It was the difference between the total cross-section and the scattering cross-section, and its dimension and area were the same. Cross Section: - It is defined by the equation: ?= Nv?(where N is the number density of the target nucleus and v is the neutron velocity). The microscopic cross-section has the dimension of the inverse length, and the common unit is cm. Its physical meaning was the probability of a neutron undergoing a nuclear reaction per unit distance in the medium. The influencing factors included the energy of the incident neutron, the characteristics of the medium, and its distribution. According to the neutron number decay law, I = I exp(-Nv sigmax)(the decay law under the microscopic cross-section expression), it can also be written as I = I exp(-sigmax)(the decay law under the microscopic cross-section expression). <a href="/?from=ask_words" style="color:red" target="_blank">Read more exciting novels for free</a>
Neutron distribution and shielding design of the reactor
Neutron distribution in a reactor was one of the core research contents of reactor physics. For a single neutron, the trajectory of its movement in the medium was a chaotic broken line. The movement was random until it was absorbed or escaped from the surface of the reactor. However, from the statistics of a large number of neutrons, their microscopic behavior could be described. In the core of a large reactor, the spatial distribution of neutrons was close to the same, and it could be assumed that it had nothing to do with the direction of motion, which simplified the problem. The neutron transport equation could accurately represent the space, energy, and direction distribution of neutrons, but it was very complicated and difficult to solve. In actual reactor physics calculations, it was only used for some local areas that needed precise calculations or as a benchmark for comparison. One could also establish a relationship between the production and disappearance of neutrons in the reactor to obtain the neutron dispersion equation to describe the distribution of neutrons in the reactor. In terms of shielding design, since neutrons were extremely harmful to the human body, the focus of reactor shielding design was to understand the proportion (or probability) of neutrons penetrating the shield, which was crucial for the safe operation of the reactor. Lead was usually used as a shielding material to surround the reactor to block or weaken the various rays emitted by the reactor. Assuming that the shielding layer was an ideal uniform lead plate, and the swimming distance between the two successive collisions of neutrons in the shielding layer followed an exponential distribution, the traditional Monte-Carlo method could be used to calculate the proportion of neutrons penetrating the shielding layer. The Monte-Carlo imitation convergence method could also be used to calculate the thickness of the shielding layer when the penetration rate was a certain value, and then the computer search method could be used to calculate the thickness of the shielding layer when the probability of neutrons penetrating the shielding layer was very small. <a href="/?from=ask_words" style="color:red" target="_blank">Read more exciting novels for free</a>
Graphite-slowed thermal neutron reactor
Graphite - moderated thermal neutron reactor. <a href="/?from=ask_words" style="color:red" target="_blank">Read more exciting novels for free</a>
How to say reactor neutron in English
The " reactor neutron " could be " reactor neutron." <a href="/?from=ask_words" style="color:red" target="_blank">Read more exciting novels for free</a>
Low neutron flux density experimental reactor
The low neutron flux density experimental reactor was an experimental reactor. In the existing research, there were many studies related to reactors that involved the concept of neutron flux density. It represented the sum of the distance traveled by all neutrons in a unit volume in a unit time. It was an important factor in nuclear reactors and directly affected the fission reaction rate of nuclear reactors. The experimental reactor with low neutron flux density could be used to carry out various research related to low flux conditions, such as the performance of some materials under low neutron flux density, the reaction characteristics of specific reactions under such conditions, etc. However, there was no more detailed information on its specific use in the current reference materials. <a href="/?from=ask_words" style="color:red" target="_blank">Read more exciting novels for free</a>
Is the reactor 201 or 304?
201 stainless steel contains high Manganese, low Ni, poor corrosion resistance, easy to rust;304 stainless steel contains more Chromite, easy to rust, strong corrosion resistance. When choosing the reactor to use 201 or 304 stainless steel, it is necessary to consider the corrosion resistance requirements of the working environment of the reactor. If the working environment is not corrosive and sensitive to cost, 201 stainless steel can be considered; if the working environment has certain corrosive requirements, 304 stainless steel is more suitable. At the same time, we must also consider the standards and specifications of different industries. For example, in industries such as medicine and food that have high requirements for hygiene and corrosion resistance, 304 stainless steel may be a better choice. <a href="/?from=ask_words" style="color:red" target="_blank">Read more exciting novels for free</a>
neutron feedback
" Neutron " is " neutron "," feedback " is " feedback ", and " neutron feedback " can be " neutron feedback ". <a href="/?from=ask_words" style="color:red" target="_blank">Read more exciting novels for free</a>
The Corpse Breeder
" The Zombie Breeder " was not a proper online novel name. It might be a derivative name of a certain novel. If you need more information, please provide me with more information. I will try my best to answer your questions. The original manga " Under One Man " was equally exciting. Just click the button to download the App and enjoy the exciting content!