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Evaluation of various calculational models of FA containing burnable absorber rod in the VVER-1000

  • Sahar Ghaseminejad and Mohammadhadi Porhemmat EMAIL logo
Published/Copyright: May 23, 2025
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Abstract

The economic performance of a nuclear reactor is fundamentally linked to optimizing fuel efficiency, extending burn-up, and ensuring safe operational parameters. In this regard, this research explores the influence of lattice computational models on macroscopic cross-section generation for VVER-1000 Fuel Assemblies (FAs) containing Burnable Absorber Rods (BARs), focusing on their impact on neutronic parameters throughout the first operational cycle. The study addresses the spectral hardening effect of BARs, which causes distinct neutronic behaviors in fuel rods based on their proximity to the absorber. Three FA simulation arrangements are compared to assess the neutronic consequences of these proximity effects. Results highlight the increased plutonium isotope production and reduced uranium-235 consumption in fuel rods adjacent to BARs. A comparative study of key core parameters during the cycle, such as boron concentration and power peaks, is presented to demonstrate the effects of BAR modeling. The WIMD-D4 transport lattice code, with an updated library by the IAEA, and PARCS, which leverages advanced nodal kernel and CITATION finite difference codes for core calculation, are utilized in this research.


Corresponding author: Mohammadhadi Porhemmat, Reactor and Nuclear Safety School, Nuclear Science and Technology Research Institute (NSTRI), P.O. Box: 143995113, Tehran, Iran, E-mail:

Nomenclature

FA

Fuel Assembly

BARs

Burnable Absorber Rods

NPP

Nuclear Power Plant

HFP

Hot Full Power

PMAXS

Purdue Macroscopic XS

PARCS

Purdue Advanced Reactor Core Simulator

PPM

Parts Per Million

VVER

water-water energetic reactor

WIMS

Winfrith Improved Multigroup Scheme

  1. Research ethics: Not applicable.

  2. Informed consent: Informed consent was obtained from all individuals included in this study, or their legal guardians or wards.

  3. Author contributions: All authors have accepted responsibility for the entire content of this manuscript and approved its submission. OR in the case of a single author contribution. The author has accepted responsibility for the entire content of this manuscript and approved its submission.

  4. Use of Large Language Models, AI and Machine Learning Tools: None declared.

  5. Conflict of interest: The authors state no conflict of interest.

  6. Research funding: None declared.

  7. Data availability: Not applicable.

References

Askew, J., Fayers, F., and Kemshell, P. (1966). General Description of the Lattice code WIMS. Atomic Energy Establishment, Winfrith, Eng.Search in Google Scholar

Ghaseminejad, S., Hadad, K., Porhemmat, M., and Rabiee, A. (2023). Evaluation of time dependent neutron transport algorithms using 2D modular ray tracing MOC. Prog. Nucl. Energy 163: 104833, https://doi.org/10.1016/j.pnucene.2023.104833.Search in Google Scholar

Hadad, K. and Porhemmat, M. (2015). SARCS cross section library generator: Part two: fast and quasi transients evaluations. Prog. Nucl. Energy 83: 347–355, https://doi.org/10.1016/j.pnucene.2015.04.008.Search in Google Scholar

Halsall, M. (1980). A summary of WIMS/D4 input options, AEEW-M 1327. A. Energy Establ., Winfrith, UK,(July, 1990).Search in Google Scholar

Iran, A.E.O.O. (2007). Album of neutron and physical characteristics of the 1st loading of Bushehr nuclear plant. In: IRAN, A.E.O.O. (Ed.). Tehran-Iran: atomic energy Organization of Iran. Atomic Energy Organization of Iran, Tehran, Iran.Search in Google Scholar

Pazirandeh, A., Ghaseminejad, S., and Ghasemiejad, M. (2011). Effects of various spacer grid modeling on the neutronic parameters of the VVER-1000 reactor. Ann. Nucl. Energy 38: 1978–1986, https://doi.org/10.1016/j.anucene.2011.04.020.Search in Google Scholar

Porhemmat, M., Hadad, K., and Faghihi, F. (2015). PARCS cross-section library generator; part one: development and verification. Prog. Nucl. Energy 78: 155–162, https://doi.org/10.1016/j.pnucene.2014.08.008.Search in Google Scholar

Rotj, M., MacDougall, J., and Kemshell, P. (1967). The Preparation of input Data for WIMS. Atomic Energy Establishment, Winfrith (England).Search in Google Scholar

Vondy, D., Cunningham, G., and Fowler, T. (1971). Nuclear reactor core analysis: CITATION. Oak Ridge National Lab, USA.Search in Google Scholar

Wagner, J. (2001). Parametric Study of the Effect of burnable poison Rods for PWR burnup credit. ORNL Oak Ridge National Laboratory (US), USA.10.2172/814219Search in Google Scholar

Winters, J., Vijuk, R., and Cummins, W. (2004). AP1000 design control document. Westinghouse Electric Company LLC, Pittsbrugh, PA, US.Search in Google Scholar

Received: 2025-01-02
Accepted: 2025-04-22
Published Online: 2025-05-23
Published in Print: 2025-06-26

© 2025 Walter de Gruyter GmbH, Berlin/Boston

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