THE SPATIAL AVERAGING OF REACTOR VARIABLES IN TRANSIENT CALCULATIONS

摘要

In many cases of practical importance it is possible in transient calculations to consider only axial variations of flux distribution and to use a one-dimensional model of the reactor. In other oase3 it is adequate to take averages over the whole reactor. However in all these cases it is necessary to have a well founded method of obtaining the averages of reactor variables.nSome effects which are strictly three-dimensional, but which can be calculated separately, such as leakage changes arising from flux variations due to control absorber movement, can be included.nThis paper presents the appropriate form of the one-group diffusion equation and delayed neutron equations for a one-dimensional axial analysis and for a whole reactor mean model. Expressions are derived for the modifications to the standard equations introduced by the movement of control absorbers.