Explanation

The quotient obtained by dividing the number of neutrons entering an appropriate small sphere centered at a certain point in space per unit time by the maximum cross-sectional area of the sphere. It is also called neutron fluence for short. The irradiation effect of nuclear fuel and reactor materials in the irradiation field is related to neutron flux density, neutron energy spectrum and fluence. The prediction and measurement of neutron irradiation dose is very important.

Classification