Application of ATHLET/DYN3D coupled codes system for fast liquid metal cooled reactor steady state simulation

International Conference for Young Scientists, Specialists, and Postgraduates on Nuclear Reactor Physics 2016

Ivanov, V.^1 ; Samokhin, A.^1 ; Danicheva, I.^1 ; Khrennikov, N.^1 ; Bouscuet, J.^2 ; Velkov, K.^2 ; Pasichnyk, I.^2

Scientific and Engineering Centre for Nuclear and Radiation Safety (SEC NRS), Malaya Krasnoselskayast 2/8, bld. 5, Moscow

107140, Russia^1

Gesellschaft für Anlagen- und Reaktorsicherheit (GRS), Forschungszentrum, Boltzmannstraße 14, Garching bei München

85748, Germany^2

关键词: Calculation results;    Outlet temperature;    Reactivity transients;    Reactor transients;    Steady-state condition;    Steady-state simulations;    Temperature and pressures;    Thermohydraulic calculations;   

Others  :  https://iopscience.iop.org/article/10.1088/1742-6596/781/1/012034/pdf
DOI  :  10.1088/1742-6596/781/1/012034

来源: IOP

【 摘 要 】

In this paper the approaches used for developing of the BN-800 reactor test model and for validation of coupled neutron-physic and thermohydraulic calculations are described. Coupled codes ATHLET 3.0 (code for thermohydraulic calculations of reactor transients) and DYN3D (3-dimensional code of neutron kinetics) are used for calculations. The main calculation results of reactor steady state condition are provided. 3-D model used for neutron calculations was developed for start reactor BN-800 load. The homogeneous approach is used for description of reactor assemblies. Along with main simplifications, the main reactor BN-800 core zones are described (LEZ, MEZ, HEZ, MOX, blankets). The 3D neutron physics calculations were provided with 28-group library, which is based on estimated nuclear data ENDF/B-7.0. Neutron SCALE code was used for preparation of group constants. Nodalization hydraulic model has boundary conditions by coolant mass-flow rate for core inlet part, by pressure and enthalpy for core outlet part, which can be chosen depending on reactor state. Core inlet and outlet temperatures were chosen according to reactor nominal state. The coolant mass flow rate profiling through the core is based on reactor power distribution. The test thermohydraulic calculations made with using of developed model showed acceptable results in coolant mass flow rate distribution through the reactor core and in axial temperature and pressure distribution. The developed model will be upgraded in future for different transient analysis in metal-cooled fast reactors of BN type including reactivity transients (control rods withdrawal, stop of the main circulation pump, etc.).