Quantcast Neutron Flux  Custom Search DOE-HDBK-1019/1-93 Reactor
Theory (Neutron Characteristics) NUCLEAR CROSS SECTIONS AND
NEUTRON FLUX Rev. 0 Page 15 NP-02 Neutron Flux Macroscopic cross
sections for neutron reactions with materials determine the
probability of one neutron undergoing a specific reaction per
centimeter of travel through that material.  If one wants to
determine how many reactions will actually occur, it is
necessary to know how many neutrons are traveling through the
material and how many centimeters they travel each second. It is
convenient to consider the number of neutrons existing in one
cubic centimeter at any one instant and the total distance they
travel each second while in that cubic centimeter.  The number
of  neutrons  existing  in  a  cm   of  material  at  any
 instant  is  called  neutron  density  and  is 3 represented by
the symbol n with units of neutrons/cm .  The total distance
these neutrons can 3 travel each second will be determined by
their velocity. A good way of def