MODELLING REACTOR KINETICS USING DIFFERENT SETS OF DELAYED NEUTRON DATA

Authors & Affiliations

Abramov B.D.
Institute for Physics and Power Engineering, Obninsk, Russia

Abstract

Some reactor kinetics mathematical modelling problems are considered in the framework of the standard 6- group delayed neutron constants (Keepin, ABBN, JENDL, ENDF/B6) with energy and isotope dependent precursor half-lives, and the new 8-group delayed neutron data (Spriggs, Campbell, Piksaikin) with "universal" precursor decay constant (or half-life) groups identical for all isotopes and energies.

Keywords
6-group delayed neutron constants, Keepin, ABBN, JENDL, ENDF/B6, isotope dependent precursor half-lives, 8-group delayed neutron data, reactor kinetics, mathematical modelling, problems

Article Text (in English, PDF, Translated by IAEA)

References

UDC 621.039.51

Problems of Atomic Science and Technology. Series: Nuclear Constants", issue 1-2, 2003