Investigation of Thermal and Epithermal Neutron Flux Distributions in Universal Nuclear Icebreaker Fuel Assemblies

Samoilov, O. B.; Алексеев, В. И.; Galitskikh, V. Yu.; Belin, Amaury; Zaglyadnov, A. N.; Samusenkov, V. V.; Ust’yantsev, S. G.

doi:10.1007/s10512-017-0217-0

Cited by 3 publications

(1 citation statement)

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“…An innovative core with an increased energy resource was used when designing RITM-200 reactor unit. Fuel assemblies are enclosed in hexagonal covers, installed central displacer with a safety control rod and fuel rods bundle [1][2][3][4][5][6][7][8][9][10][11]. The design features of the fuel assembly necessitated the determination of important hydraulic characteristics, such as the distribution of the coolant flow rate in the subchannels at the inlet to the fuel rods bundle.…”

Section: Introductionmentioning

confidence: 99%

Experimental studies and numerical simulation of coolant hydrodynamics in the inlet area of nuclear reactor fuel assembly

et al. 2018

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An innovative core with an increased energy resource was used when designing RITM-200 reactor unit. The paper presents the results of experimental and numerical simulation of hydrodynamic processes occurring in the inlet region of the RITM reactor fuel assembly model. Computational mesh of fuel assembly, containing ~ 22 million elements was created using Ansys ICEM CFD. The values of relative axial velocities in several cross sections at the inlet to the bundle of fuel elements are obtained. At the inlet to the fuel rods bundle the velocity field is not uniform, due to the complex geometry of the fuel assembly. The obtained results of CFD-simulation can be used to determine the input boundary conditions for subchannel programs of the core thermal-hydraulic analysis. This allows taking into account uneven flow rate distribution in subchannels due to the complex geometry of the fuel assembly inlet region.

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