neutron moderation
neutron moderation
Neutron moderation
Neutron absorption is the process wherein an atomic nucleus will absorb a neutron. Many different atomic nuclei will do this, and different nuclei will present a larger of smaller target for the neutron, as you might have guessed. This is the neutron absorption cross section for the material, and it varies as the material does and as the kinetic energy of the neutron does, as well. You may have figured out that there are many different resulting products or outcomes that can be seen from neutron absorption. It is neutron absorption that powers up a chain reaction, so let's look at that aspect of this phenomenon. In a nuclear reactor, some spontaneous fissions will release neutrons, and these neutrons will, if the control rods are pulled out sufficiently, begin a chain reaction. The nuclear fuel, usually either uranium or plutonium, will absorb a neutron (after some slowing down of that neutron), and they'll fission as a result. These fissions will release more neutrons, which will be absorbed and will create more fissions, which will release more neutrons, etc. A neutron released from a fission event will have a high kinetic energy; it will be moving very quickly. It might be absorbed, but will have a higher probability of being absorbed if it is slowed down, or thermalized. The moderator in a reactor, usually water, does this slowing down of the neutrons. The slower neutrons have a much higher probability of being absorbed and continuing the chain. Fission by neutron absorption is the mechanism by which a nuclear chain reaction is maintained in a nuclear reactor.
Through collisions of neutrons with nuclei of the moderator kinetic energy is transfered to the moderator slowing the neutrons.
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The material used to slow down high-speed neutrons in a reactor is called the moderator. The moderator in a pressurized water reactor is the water, which is the main coolant. Collisions between the neutron and hydrogen nuclei (protons) slow the neutron down (thermalizing it) and increasing the probability that it will be absorbed by another fissionable atom. That makes the chain go, it maintains the chain reaction. Slowing down neutrons does NOTslow down the process of nuclear fission. If anything, it maintains it or speeds it up because slower moving neutrons have a higher probability of being absorbed and continuing or building the chain reaction. A link is provided.
We Increase Friction when we are stopping a car, bike or when slowing down to a way up.
The moderator in a nuclear power plant is the substance that is used to slow down neutrons that are generated by the fission reactions. When fissile material fissions, fission fragments appear, as do neutrons. These neutrons, which leave the fission reaction with a heap of kinetic energy, might go on to cause more fissions (in a chain reactions) if they can be thermalized (slowed). Slowing (moderating) the neutrons increases the probability that they will be absorbed to cause another fission.Depending on the plant design, a few common ones now are:waterheavy watergraphitenone (in fast breeder reactors)
because of global warming and increase of doldrums.
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same as ordinary water, but the heavier Deuterium atoms are more effective at slowing neutrons to thermal energies.
Arne Claesson has written: 'Space-, time-, energy-dependent slowing down of neutrons in hydrogen and deuterium' -- subject(s): Deuterium, Hydrogen, Neutrons, Stopping power (Nuclear physics)