Measurement of neutron radiation characteristics to reconstruct the energy distribution of neutron flux density.
Obtained energy distribution of neutron flux density is used to calculate such values as:
– Integral neutron flux density
– Average energy of neutron radiation by spectrum
– Average energy of neutron radiation by dose
– Dose equivalent per unit flux density
– Dose equivalent
– Effective dose
▪ Ready-to-use measurement procedures
▪ Advanced set of spherical polyethylene moderators is available with the following diameters: 3.5″; 4.5″; 5″; 7″; 9″; 9.5″
