A Matrix Operator Method for Reactor Calculation

概要

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As a means of numerically computing neutron flux distribution, a matrix operator method is considered. In this method time, space and neutron energy are discretized, i, e., considered as discrete variables, and the operators describing the neutron motion are defined in each interval of the discrete variables. The operators consist of space and energy operators, which describe the spatial and the energy distribution of the neutron flux respectively. The operation of these matrix operators on the collision density and the pseudo neutron flux vectors yields the neutron flux distribution of the entire system.<BR>This method may be considered an extension to space of the conventional multi-energy treatment, and eliminates tedious procedures to take account of boundary and initial conditions. It eases moreover the selection of time interval from the computational point of view.
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