Neutronic and thermal-hydraulic assessment of the TRR with new core designed based on tubular fuels
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Rahman Gharari
,
Mostafa Hasanzadeh
Abstract
Herein, the feasibility study of the Tehran Research Reactor (TRR) with a new core designed based on tubular fuels from the neutronic, thermal-hydraulic, safety, and operational points of are investigated using MCNPX, WIMS, CITATION, Computational Fluid Dynamics (CFD), and RELAP codes. According to the results, the total neutron flux in the new core with tubular fuels is increased by more than 14.3 % compared with the current core of the TRR with plate-type fuels. Moreover, due to the higher fuel amount in the tubular compared with plate-type fuels (about 17 % in similar conditions), its effective multiplication factor is much higher than the TRR with plate-type fuels. Moreover, the results show that the maximum cladding temperature is sufficiently lower than 105 °C and the produced heat in the tubular fuel are removed without changing the current flow rate of the core. Furthermore, the maximum fuel temperature in tubular fuel is about 10 °C lower than the maximum fuel temperature in the current standard fuel element.
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Research ethics: Not applicable.
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Author contributions: R. Gharari: Software, Formal analysis, Writing-Original Draft, Visualization M. Hasanzadeh: Supervision, Project administration, Software, Conceptualization F. Khoshahval: Supervision, Project administration, Software, Conceptualization, Writing-Review & Editing M. A. Mozaffari: Software, Conceptualization, M. A. Amirkhani Dehkordi: Software, Formal analysis, Visualization, H. Esmaili: Software, Formal analysis, Visualization.
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Competing interests: The authors state no conflict of interest.
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Research funding: None declared.
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Data availability: Data will be provided on request.
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Articles in the same Issue
- Frontmatter
- CFD modeling of natural convection in pebble bed geometry with finite volume method
- Experimental investigation of heat transfer characteristics of inclined aluminium two phase closed thermosyphon
- Advances in triple tube heat exchangers regarding heat transfer characteristics of single and two-phase flows in comparison to double tube heat exchangers part 1
- Advances in triple tube heat exchangers regarding heat transfer characteristics of single and two-phase flows in comparison to double tube heat exchangers part 2
- Neutronic and thermal-hydraulic assessment of the TRR with new core designed based on tubular fuels
- A non-dominated discrete differential evolution for fuel loading pattern optimization of a nuclear research reactor
- CFD and machine learning based hybrid model for passive dilution of helium in a top ventilated compartment
- Optimization strategy for SAM in nuclear power plants based on NSGA-II
- Probing 6He induced reactions with nuclear level density
- An application for nonlinear heterogeneity-based isotherm models in characterization of niobium sorption on clay rocks and granite
- Calendar of events
