Computational analysis of nuclear desalination system under various configurations
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Salah Ud-Din Khan
und
Jamel Orfi
Abstract
The research addressed the economic evaluation of nuclear energy, coal, oil and natural gas in various cycle configurations with different distillation technologies. A comparison between fossil and nuclear energy sources is discussed. A comprehensive review of all desalination plants using fossil and nuclear energy with cogeneration is also included and discussed. Computational model was used to evaluate nuclear and non-nuclear desalination plants. Four possibilities were discussed. In this first case, a nuclear gas cycle integrated with a MED desalination plant was found to have the lowest cost in the gas cycle. While the nuclear steam cycle integrated with RO has the lowest cost compared to oil and natural gas. In the third case, the combined nuclear cycle was discussed and it was found that the combined nuclear cycle associated with RO has the lowest cost. In the last case, the evaluation of a heat-only desalination plant was conducted among all sources, and it was found that the nuclear plant with RO and MED has the lowest cost. In addition, the completed nuclear desalination plant was subjected to five scenarios to calculate and estimate at which capacity the plant provides the best values. The results show that nuclear desalination with gas cycle is the most economical among the oil and natural gas options.
Funding source: National Plan for Science, Technology and Innovation (MAARIFAH), King Abdulaziz City for Science and Technology
Award Identifier / Grant number: 2-17-02-001-0056
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Author contributions: Conceptualization, S.U.-D.K. and J.O.; methodology, S.U.-D.K.; software, Khan, S.U.-D.K.; validation, S.U.-D.K. and J.O.; formal analysis, J.O.; investigation, S.U.-D.K.; resources, S.U.-D.K.; data curation, S.U.-D.K. and J.O.; writing – original draft preparation, S.U.-D.K.; writing – review and editing, S.U.-D.K. and J.O.; visualization J.O.; supervision, S.U.-D.K.; project administration, J.O;
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Research funding: This research was funded by National Plan for Science, Technology and Innovation (MAARIFAH), King Abdulaziz City for Science and Technology, grant number 2-17-02-001-0056.
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Conflict of interest statement: The authors declare no conflicts of interest regarding this article.
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© 2023 Walter de Gruyter GmbH, Berlin/Boston
Artikel in diesem Heft
- Frontmatter
- Scaling effect on cesium diffusion in compacted MX-80 bentonite for buffer materials in HLW repository
- Enhanced heat transfer in corrugated plate fin heat sink
- Discussion of options to increase the control drum worth in fast reactor
- New semi-empirical systematic of (p,n) reaction cross section at 7.5 MeV
- Computational analysis of nuclear desalination system under various configurations
- Performance analysis of nuclear powered desalination unit based on MED-TVC: a case study for Saudi Arabia
- Analysis of 4-inch cold leg top-slot break LOCA in ATLAS experimental facility using MARS-KS
- Evaluating the performance of Indonesia’s nuclear energy program using INPRO methodology
- Thermal hydraulic analysis of VVER spent fuels stored in vault dry system under different operating and design conditions
- Comparative analysis of swelling and porosity evolution in UO2 fuel via two approaches
- Euler–Maruyama algorithm in estimating UGV path and location in nuclear emergency and security applications
- Modeling and simulation of deposited energy gain via irradiation of heavy ion beams on the fusion reactor contains spherical fuel capsules with foam
- Calendar of events
Artikel in diesem Heft
- Frontmatter
- Scaling effect on cesium diffusion in compacted MX-80 bentonite for buffer materials in HLW repository
- Enhanced heat transfer in corrugated plate fin heat sink
- Discussion of options to increase the control drum worth in fast reactor
- New semi-empirical systematic of (p,n) reaction cross section at 7.5 MeV
- Computational analysis of nuclear desalination system under various configurations
- Performance analysis of nuclear powered desalination unit based on MED-TVC: a case study for Saudi Arabia
- Analysis of 4-inch cold leg top-slot break LOCA in ATLAS experimental facility using MARS-KS
- Evaluating the performance of Indonesia’s nuclear energy program using INPRO methodology
- Thermal hydraulic analysis of VVER spent fuels stored in vault dry system under different operating and design conditions
- Comparative analysis of swelling and porosity evolution in UO2 fuel via two approaches
- Euler–Maruyama algorithm in estimating UGV path and location in nuclear emergency and security applications
- Modeling and simulation of deposited energy gain via irradiation of heavy ion beams on the fusion reactor contains spherical fuel capsules with foam
- Calendar of events
