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ANS 19.3 2011 Edition, January 1, 2011
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Steady-state neutronics methods for power reactor analysis
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This standard provides guidance for performing and validating the sequence of steady-state calculations leading to prediction—in all types of operating commercial nuclear reactors—of the following:

(1) reaction-rate spatial distributions;

(2) reactivity;

(3) change of nuclide compositions with time.

The standard provides the following:

(1) guidance for the selection of computational methods;

(2) criteria for verification and validation of calculation methods used by reactor core analysts;

(3) criteria for evaluation of accuracy and range of applicability of data and methods;

(4) requirements for documentation of the preceding.

Note that the use of mixed uranium-plutonium oxide (MOX) fuel has been taken as out of scope for this revision of the standard. It will be taken into account in the next revision.