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Validation of the Coupled System Code ATHLET/BIPR-VVER on Local Core Measured Data

[+] Author Affiliations
S. Nikonov, M. Lizorkin

RRC KI, Moscow, Russia

S. Langenbuch, K. Velkov

GRS mbH, Garching, Germany

Paper No. ICONE16-48604, pp. 457-462; 6 pages
doi:10.1115/ICONE16-48604
From:
  • 16th International Conference on Nuclear Engineering
  • Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition
  • Orlando, Florida, USA, May 11–15, 2008
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 0-7918-4815-9 | eISBN: 0-7918-3820-X
  • Copyright © 2008 by ASME

abstract

The modern coupled thermal-hydraulics neutron–kinetics code systems require validation by comparison with measured local core data. Measured assembly coolant temperatures at core outlet are applied for this purpose in this study. Experimental data have been collected during the commissioning phase of the NPP Kalinin-3. One of the experimental data sets is selected to be used for international benchmark purposes (1). The new modelling capabilities of the ATHLET/BIPR-VVER code as well as the validation on plant measurements are discussed in the paper. The detailed modelling features of the reactor core allow to predict the coolant temperature at the assembly outlet within a rather high accuracy even though ATHLET code is based on one dimensional thermal-hydraulic pipe models.

Copyright © 2008 by ASME

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