'Leakage Iteration': A procedure for taking into account neutron leakage in cell calculations

A method is presented for a numerical evaluation of the space and energy dependent neutron flux in heterogeneous regions of finite size by an iterative procedure. The work contains three steps: The solution of the transport equation by a B1 multigroup multiregion approximation 1) for a perfectly reflected heterogeneous cell, 2) for an equivalent homogeneous region of finite size, respectively. In part 3) a prescription is given how to obtain the homogeneous parameters from step 1) and how to obtain leakage corrected cross sections from step 2). (Auth.)