The neutron integral transport dynamic equation

The neutron integral transport dynamic equation is presented on the basis of a fundamental theory analysis. The presentation of this equation is a development of the neutron integral transport theory. It enables the integral transport theory not only to solve the heterogeneous cell parameter problems but also to solve reactor dynamic problems. Neutron integral transport dynamic equation is a multi-group and multi-point (one sub-zone is one point) dynamic equation. It is only a multi-point dynamic equation for single group problem. The multi-group and multi-point equation can be used to analyse the spectrum time variation in different points and the multi-point dynamic equation can be used to analyse the space dependent neutron dynamic behavior. In second part of this paper an application example of the integral transport dynamic equation is presented. The problem of composition of neutron generation time for China Advanced Research Reactor (CARR) is analysed. (author)