Neutron reactor
A neutron reactor could be a Neutron reactor. Read more exciting novels for free
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>
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>
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. <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>
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>
Neutron Star novels
It was known that the author, Neutron Star, had an online novel,[Interstellar] Professional Destruction of Three Concepts.] <a href="/?from=ask_words" style="color:red" target="_blank">Read more exciting novels for free</a>
The filter in the photocatalysis reactor
The optical filter in the photocatalysis reactor played an important role in many aspects. First of all, it could filter light and only allow light of a specific wavelength to pass through, thereby achieving fine control of the reaction light source, which helped to improve the specialization and efficiency of the biochemical reaction. Secondly, different filter had different spectral transmissances, which could be used to control the light intensity and spectral distribution during the reaction process. This would not only help in the optimization of experimental conditions and increase the purity and yield of the product, but also help to reduce the occurrence of side reactions and reduce energy consumption and experimental costs. In addition, the filter also had the function of protecting the photocatalysis reactor. Some light sources would generate high temperatures during long-term operation, which could cause the performance of the instrument to decline or even be damaged. The filter could effectively filter out excess light and reduce the heat of the light source, thereby extending the service life of the instrument. <a href="/?from=ask_words" style="color:red" target="_blank">Read more exciting novels for free</a>
byd reactor principle
In the BYD reactor, fresh and recycled formalin from the formalin plant entered the liquid phase of the BYD reactor, while the ethyne gas entered the bottom of the reactor and dispersed in the liquid-solid phase. Under the effect of the catalyst, the reaction occurred to form 1,4-butynegol (C2H2 + 2HHamster → HOCH2C = ccH20H (BYD)). After the pulp in the ByD reactor was filtered by the candle filter in the reactor, the filtered liquid entered the ByD collection tank (BD-V104). The reactor's internal components included a candle filter, an ethyne loop, a stirring device, a cooling coil, etc. The shell was made of Q345R + 316L. <a href="/?from=ask_words" style="color:red" target="_blank">Read more exciting novels for free</a>
Nuclear fission in the reactor
Take Uranium-235 as an example. When the nucleus of Uranium-235 was bombarded by external neutrons, one nucleus would absorb a neutron and split into two smaller nuclei, releasing two to three neutrons at the same time. The neutrons produced by the fission bombarded another Uranium-235 nucleus, causing new fission. If this continued, it would be a fission chain reaction, which would produce a large amount of heat. In order to achieve such a nuclear fission reaction, the reasonable structure of the reactor should include nuclear fuel, moderator, heat carrier, control facilities, and protective devices. The nuclear fuel needed to be made from uranium ore through processes such as selection, crushing, acid soaking, and concentration to produce a certain amount of uranium and a certain geometric shape of the rod. In a traditional nuclear fission reactor, in order to improve the chain fission reaction efficiency of nuclear fuel, it was necessary to decelerate the high-speed neutrons (fast neutrons) produced by fission into slower neutrons (thermal neutrons). A neutron moderator composed of lighter nuclei (such as light water, heavy water, etc.) would be added to use the hydrogen atoms to decelerate the high-speed neutrons. The heat carrier could be used to take away heat to prevent the reactor from burning down due to overheating. The heat that was extracted could turn the water nuclear reactor into steam to drive the gas turbine to generate electricity. The control facility allowed the nuclear reactor to operate according to human wishes. The protective device was because uranium and fission products were highly radioactive and could cause harm to humans. In addition to the traditional reactors that used Uranium-235 as nuclear fuel, there were also fast neutron reactors (nuclear fission reactors without neutron moderators) and thorium-based molten salt reactors (fourth-generation reactor nuclear energy systems that used thorium as nuclear fuel and composite fluorides as coolants). Their nuclear fission reaction principles were similar, but there were differences in specific fuel, efficiency, safety, and so on. <a href="/?from=ask_words" style="color:red" target="_blank">Read more exciting novels for free</a>
Is the cracking precipitator a reactor?
The FCCU consisted of a reactor (discharger), a regenerating, and other equipment. The discharger was a part of the reactor. It was not an overall concept of the reactor in a separate sense, but a component of the reactor that carried specific functions in the FCCU reaction system. <a href="/?from=ask_words" style="color:red" target="_blank">Read more exciting novels for free</a>