Validation results of the BIPR-8A code, the new module of the software package KASKAD.

Soshitov N.P., Tomilov M.Y., Yasnopolskaya I.I.

29th Symposium of AER on VVER Reactor Physics and Reactor Safety (2019, Energoland, Mochovce NPP, Slovakia)
reactor physics experiments and code validation


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 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.
The operational data used for comparison were obtained on the units of the following nuclear power plants: Kalinin NPP, Novovoronezh NPP-2, Leningrad NPP-2, Rostov NPP, Kola NPP.
The calculation results obtained by using Monte Carlo codes MCU-PD and MCNP are presented for the calculation models of the following first and stationary fuel cycles: VVER-1000 – ETE benchmark, Tianwan NPP, Rostov NPP, Novovoronezh NPP-2, Hanhikivi NPP and VVER-TOI.

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