This paper presents the current status of works performed to date to further upgrade fuel assemblies and fuel cycle of WWER-440 reactors, and also considers some innovations – both envisaged and implemented in practice – intended to improve their neutronic and operating parameters. Reactors were assumed to operate at 100% power in a steady-state refueling mode. Trial operation of third-generation fuel assemblies (FA-3), including a comparison between some calculated and measured results, is described as an example illustrating these new developments.
The BIPR-8A executable module is a main component of the BIPR 2007 code. This module is intended for three-dimensional coarse mesh calculation of the VVER reactor cores. This paper presents the results of validation of the BIPR-8A executable module. Validation is based on comparison of the calculated results with the operating data of power plants with the VVER-440, VVER-1000 and VVER-1200 reactors, and with the results of calculations obtained by using Monte Carlo codes. The results of comparison of the following values at HZP (hot zero power) power level and operational power level are presented: critical concentration of boric acid, temperature reactivity coefficient, efficiency of the control rods system, relative power distribution of fuel assemblies and 3D power distribution, effective multiplication factor.
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