Augmentation of the neutronic safety aspect of high-density fuel research reactor using new control element design
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Mohammad Hadi Porhemmat
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Mostafa Hassanzadeh
Abstract
The development of a 10 MW research reactor core using high-density U3Si2–Al plate fuel is presented, focusing on enhancing neutronic safety through optimized core configuration and control element design. This study employs MCNP and CITATION codes to evaluate neutronic parameters, including Power Peaking Factor (PPF) and Stuck Rod Shutdown Margin (SRSM). By incorporating four symmetrical irradiation boxes in the core center, the PPF is reduced by approximately 5 %, distributing neutron flux more uniformly. A novel control assembly design with a thin D2O layer increases control rod worth ensuring SRSM <−1,000 pcm without additional absorber material. Reactivity feedback analysis confirms safe operation with negative coefficients for fuel temperature and moderator conditions (−1.56 pcm/°C for D2O −20.11 pcm/°C for combined moderator temperature and density with D2O). This approach enhances safety margins and extends cycle length, offering a novel solution for high-density fuel research reactors.
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Research ethics: Not applicable.
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Informed consent: Not applicable.
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Author contributions: All authors have 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: All other authors state no conflict of interest.
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Research funding: None declared.
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Data availability: Not applicable.
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© 2025 Walter de Gruyter GmbH, Berlin/Boston
Articles in the same Issue
- Frontmatter
- Serpent 2 simulations of the historic Haigerloch B8 nuclear reactor of 1945
- Safety behaviour of a material testing reactor using U3Si2 fuel during reactivity insertion accident
- Augmentation of the neutronic safety aspect of high-density fuel research reactor using new control element design
- Analysis of neutronic performance of VVER 1200 reactor using accident tolerant fuel
- Reliability assessment of equal height difference passive containment cooling system based on the adaptive metamodel-based subset importance sampling method in inverse uncertainty quantification framework
- Numerical investigation of three-tube intertwined HX design
- Prediction of LOCA break sizes using LSTM architecture for pressurized water reactors
- Decoupling and controller design of multivariable systems for small modular reactors
- Adsorption behavior of Se(Ⅳ) and Se(Ⅵ) on sodium bentonite
- Calendar of events
Articles in the same Issue
- Frontmatter
- Serpent 2 simulations of the historic Haigerloch B8 nuclear reactor of 1945
- Safety behaviour of a material testing reactor using U3Si2 fuel during reactivity insertion accident
- Augmentation of the neutronic safety aspect of high-density fuel research reactor using new control element design
- Analysis of neutronic performance of VVER 1200 reactor using accident tolerant fuel
- Reliability assessment of equal height difference passive containment cooling system based on the adaptive metamodel-based subset importance sampling method in inverse uncertainty quantification framework
- Numerical investigation of three-tube intertwined HX design
- Prediction of LOCA break sizes using LSTM architecture for pressurized water reactors
- Decoupling and controller design of multivariable systems for small modular reactors
- Adsorption behavior of Se(Ⅳ) and Se(Ⅵ) on sodium bentonite
- Calendar of events
