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.
Nomenclature
- FA
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Fuel Assembly
- BARs
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Burnable Absorber Rods
- NPP
-
Nuclear Power Plant
- HFP
-
Hot Full Power
- PMAXS
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Purdue Macroscopic XS
- PARCS
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Purdue Advanced Reactor Core Simulator
- PPM
-
Parts Per Million
- VVER
-
water-water energetic reactor
- WIMS
-
Winfrith Improved Multigroup Scheme
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Research ethics: Not applicable.
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Informed consent: Informed consent was obtained from all individuals included in this study, or their legal guardians or wards.
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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.
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Use of Large Language Models, AI and Machine Learning Tools: None declared.
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Conflict of interest: The authors state no conflict of interest.
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Research funding: None declared.
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Data availability: Not applicable.
References
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Articles in the same Issue
- Frontmatter
- Investigations into the development of a new type of internal pipe cutting device for difficult to access pipelines
- Study on flow field characteristics of regulator in uranium enrichment centrifugal cascade
- Innovative materials for enhancing safety, efficiency, and sustainability in nuclear waste management
- Double solitary waves reactor
- Advancing the safety design of heat pipe cooled reactors: a case study of lead liquid bath and monolith stainless steel core
- Evaluation of various calculational models of FA containing burnable absorber rod in the VVER-1000
- Accurate departure from nucleate boiling ratio (DNBR) prediction using SIMCA’s partial least squares regression and clustering
- Effect of glass cooling method on thermal shock behavior of nuclear waste container
- Study on the impact of containment mesh refinement and PAR installation on hydrogen distribution during severe accidents
- Preliminary analysis of typical accidents of CFETR helium-cooled solid breeder blanket system based on COSINE
- Calendar of events