Speaker
Description
The necessity to operatively concern the growing needs of the BN-600 reactor support as well as the commissioning of the BN-800 reactor which also has a task of scientific support have led to the necessity of a new generation simulation support code development. This new generation code would make it possible to flexibly consider actual demands of scientific support of both reactors. In future it could be also adopted for the support of the BN-1200 reactor being designed. Such a code should have more developed computational capabilities, more flexible, suitable and modern interface.
The TRIUM800 system specially developed for the computational support of the BN-800 reactor was served as a first version of the new code. The given code at this moment is widely being used in its application area. Unlike the previous system it is based on the use not only the diffusion but also the transport approximation. It is included the following program complexes as computational modules: TRIGEX (diffusion approximation; up to 26 energy groups), MMK-K and MMK-C (transport PN-approximation; Monte-Carlo technique; 26 and 299 energy groups or using the pointwise neutron data, similar to how it is done in the MCNP program). There is a possibility of an element-by-element calculation of the CPS control members and combined experimental FAs.
The development of the advanced new generation support code BNCode has been finished at this moment. This BNCode combines BN-600 and BN-800 reactors under its unified platform.
The calculated and experimental discrepancies of the CPS rods efficiency, maximum reactivity margin, criticality parameter and etc. will be demonstrated in the report during the operation of:
– hybrid BN-800 reactor core
– BN-600 reactor during the 75th between refueling period