Izvestiya vuzov. Yadernaya Energetika

The peer-reviewed scientific and technology journal. ISSN: 0204-3327

Rococo system of combined neutron constants – current status and results of testing using geometrical module of the MMK code

6/22/2018 2018 - #02 Physics and technology of nuclear reactors

Zherdev G.M. Kislitsyna T.S. Nikolaev M.N.

DOI: https://doi.org/10.26583/npe.2018.2.05

UDC: 621.039.51

Results of studies aimed at the further refinement of the ROCOCO system (routine for calculation and organization of combined constants including cross-sections in group and subgroup representation and with detailed description of neutron cross-section energy dependence) [1, 2] are presented in the present paper. Inclusion of this system as a physical module into a set of Monte Carlo calculation codes with OOBG geometric module from the MMK [3] code is discussed. OOBG module is designed for calculation of neutron multiplication systems with heterogenous cores arrange as hexagonal grids with different degrees of complexity. The complex was named ROCOCO-MMK. Results of testing the complex in the calculations of multi-zone neutron multiplication systems (including those with zones containing neutron moderator, zones with close composition but with different temperature, etc.) are described. Accounting for the dependence of constants for one and the same nuclide in the zones with different compositions and temperatures required substantial modernization of routines for preparation of constants for calculation described in [1]. Algorithm for preparation of subgroup constants was changed, methodology for taking into account resonance self-screening of cross-sections within the range of unresolved resonances was improved, and other changes were introduced in the process of this modernization.

Results of calculations are compared with data obtained using the MCNP-5 precision program [4], which is linked to the same library of evaluated neutron data ROSFOND as that used in ROCOCO. The ROCOCO-MMK includes procedures for registering different neutron flux functionals (also based on ROCOCO data), which allowed including it in the SCALA computation complex [3, 5] and step-by-step calculation of evolution of fuel nuclide composition during the fuel residence campaign. Directions of further development of the system are outlined in conclusion and, in particular, somepossibilities of using the created software for further improvement of methods for preparation of few-group constants for calculations in diffusion approximation are examined.


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new ROCOCO combined system of neutron constant preparation further refinement introduction in the practice of calculations Monte-Carlo method results of comparative calculations potential of development