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Ahmed, Farid; Abir, Atrehar; Bhowmik, Palash K.; Deshpande, Vaibhav R.; Mollah, Abdus Sattar

doi:10.1016/j.tsep.2021.100929

Cited by 12 publications

(6 citation statements)

References 49 publications

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“…The design of the high temperature gas cooled reactor concepts (GFR, V/HTR) also requires appropriate materials solutions for thermal shielding and insulation, fuel matrix, neutron reflectors and suitable control rods and seals, that would be operating close to 1000 • C, or above and up to 1650 • C in accidental scenarios [90,349] These materials must guarantee at those temperatures properties of gas-tightness and corrosion resistance, with the ability to be joined. At the moment, in addition to SiC, other materials such as C f /C, mullite (aluminosilicate), Al 2 O 3 , TiO 2 , ZrC, ZrN, Zr x Si y , B 4 C, WC, graphite or even graphene are being explored for these functions [90,[349][350][351][352].…”

Section: Annex 3-pathways To Nuclear Materials Improvement For Next G...mentioning

confidence: 99%

Materials for Sustainable Nuclear Energy: A European Strategic Research and Innovation Agenda for All Reactor Generations

Malerba

Mazouzi²,

Bertolus

et al. 2022

Energies

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Nuclear energy is presently the single major low-carbon electricity source in Europe and is overall expected to maintain (perhaps eventually even increase) its current installed power from now to 2045. Long-term operation (LTO) is a reality in essentially all nuclear European countries, even when planning to phase out. New builds are planned. Moreover, several European countries, including non-nuclear or phasing out ones, have interests in next generation nuclear systems. In this framework, materials and material science play a crucial role towards safer, more efficient, more economical and overall more sustainable nuclear energy. This paper proposes a research agenda that combines modern digital technologies with materials science practices to pursue a change of paradigm that promotes innovation, equally serving the different nuclear energy interests and positions throughout Europe. This paper chooses to overview structural and fuel materials used in current generation reactors, as well as their wider spectrum for next generation reactors, summarising the relevant issues. Next, it describes the materials science approaches that are common to any nuclear materials (including classes that are not addressed here, such as concrete, polymers and functional materials), identifying for each of them a research agenda goal. It is concluded that among these goals are the development of structured materials qualification test-beds and materials acceleration platforms (MAPs) for materials that operate under harsh conditions. Another goal is the development of multi-parameter-based approaches for materials health monitoring based on different non-destructive examination and testing (NDE&T) techniques. Hybrid models that suitably combine physics-based and data-driven approaches for materials behaviour prediction can valuably support these developments, together with the creation and population of a centralised, “smart” database for nuclear materials.

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Section: Annex 3-pathways To Nuclear Materials Improvement For Next G...mentioning

confidence: 99%

Materials for Sustainable Nuclear Energy: A European Strategic Research and Innovation Agenda for All Reactor Generations

Malerba

Mazouzi²,

Bertolus

et al. 2022

Energies

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“…They noticed that, an improvement in both the convective heat transfer coefficient (HTC) of 11.39% and the overall HTC of 7% in the presence of CuO/water nanofluids at 6.81% of area reduction. Ahmed et al 10 practically assessed the thermo-hydraulic performance of Al 2 O 3 /water, Graphene-Oxide/water, and TiO 2 / water as coolants and compared the performance parameters of these homogeneous nanofluid mixtures at 1%, 2%, and 4% volume fraction of each nanofluid along with the effect of various particle sizes on pressure drop (PD) and HT. They found that with an enhancement of HT, the PD along with an increase of the nanoparticle inclusion increases.…”

Section: Nanofluidsmentioning

confidence: 99%

“…The TEF values are shown in Figure 8 which 6,50 F I G U R E 6 Heat transfer coefficient with Reynolds number. 51 is computed using Equation (10). From Figure 8, the TEF values are increasing with the increase of shell side mass flow rate in addition to the volume concentration of Al 2 O 3 /water nanofluids.…”

Section: P P Pmentioning

confidence: 99%

Augmentation of heat transfer through passive techniques

Nitturi,

Kapu,

Gugulothu

et al. 2023

Heat Trans

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The thermal performance of energy preservation systems is greatly improved by increasing miniaturization and boosting. These are imaginative (or Promethean) techniques to enhance heat transfer. Enhancement methods of heat transfer draw great attention in front of the industrial sector because of their ability to provide energy savings and raise the economic efficiency of thermal systems. Three techniques these methods are categorized; those are active, passive, and compound. Different types of components are used in passive methods because of the transfer/working fluid flow path to the enhancement of the heat transfer rate. In this article, the subject of the review was the passive heat transfer enhancement methods including inserts (conical strips, winglets, twisted tapes, baffles), porous materials, coil/helical/spiral tubes, rough surfaces (corrugated/ribbed surfaces), extended surfaces (fins) and nanofluids (mono and hybrid nanofluid). Recent passive heat transfer enhancement techniques are studied in this article as they are cost‐effective and reliable, and also comparably passive methods do not need any extra power to promote the energy conversion systems' thermal efficiency than active methods. In the passive approaches, various components are applied to the heat transfer/working fluid flow path to improve the heat transfer rate. The passive heat transfer enhancement methods studied in this article include inserts (twisted tapes, conical strips, baffles, winglets), extended surfaces (fins), porous materials, coil/helical/spiral tubes, rough surfaces (corrugated/ribbed surfaces), and nanofluids (mono and hybrid nanofluid). From the pioneers' research work, it is clear that a lower twist ratio and lower pitch, lesser winglet angles can provide more heat transfer rate and a little bit more friction factor. In the case of nanofluids, a little bit of pumping power is enhanced. Finally, heat transfer enhancement is compared with the thermal performance factor, which is more than unity.

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“…This article's goal is to provide a concise review of key ideas in the subject of nuclear thermal hydraulics as well as the various computer programs available for simulating THrelated events with the System codes (SYS-TH), sub-channel codes, and CFD codes. The final goal of this work is to use the CFD code Ansys Fluent to assess convective heat transfer in sub-channels of rod bundles and triangle tubes of VVER-type nuclear reactors, [43], [44], [45], [46], [47], [48], [49], [50]. Additionally, CFD approaches assist in obtaining the precise temperature and flow distributions within assemblies of rod bundles in square and triangle sub-channels.…”

Section: Introductionmentioning

confidence: 99%

Recent Advances in Computational Convective Heat Transfer Study in a Sub-Channel for Nuclear Power Reactor and Future Directions

Mollah

2023

1790-5044

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A nuclear power reactor's primary use is to generate thermal energy, which in turn produces electricity. The primary heat source is a nuclear fission event occurring inside the fuel rod. The convection heat is transmitted through the coolant by the heat energy generated at the fuel rod wall boundary. Better heat transfer is produced in the flow area by turbulence and irregularity. As a result, turbulent flow heat transfer may present a significant challenge when predicting and assessing the thermal performance of nuclear power reactors. Computational techniques in convective heat transfer have become indispensable for solving challenging issues in the fields of science and engineering thanks to the development of current sophisticated numerical methods and high-performance computer hardware. The development of novel computational techniques and models for complicated transport and multi-physical phenomena is constantly in demand throughout applicable disciplines. This chapter's objective is to provide some recent developments in computational techniques for convective heat transfer, taking into account research interests in the community of mass and heat transfer, and to showcase relevant applications in nuclear power plant engineering domains including future directions. This study describes the most recent advancements in nuclear reactor convective heat transfer research utilizing the computational fluid dynamics (CFD) method, particularly at Ansys Fluent. This work examines the convective heat transfer and fluid dynamics fluid dynamics for turbulent flows across three rod bundle sub-channels that are typical of those employed in the PWR-based VVER type reactor. In this paper, CFD analysis is carried out using the software tool Ansys Fluent. Temperature distribution profile, velocity profile, pressure drop, and turbulence properties were investigated in this study. Boundary conditions i.e. temperature, velocity, pressure, heat flux, and heat generation rate were applied in the sub-channel domain. The main obstacles and bright spots for the CFD methods in nuclear reactor engineering are discussed, which helps to further its further uses. We intend to research a full-length fuel bundle model for VVER-1200 in the future to gather specific fluid characteristic data and use the findings to analyze safety and operate nuclear power facilities in Bangladesh. This paper presents a thorough analysis of the sub-channel thermal hydraulic codes used in nuclear reactor core analysis. This review discusses several facets of previous experimental, analytical, and computational work on rod bundles and identifies potential future directions based on those earlier studies.

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Thermohydraulic performance of water mixed Al2O3,TiO2

Cited by 12 publications

References 49 publications

Materials for Sustainable Nuclear Energy: A European Strategic Research and Innovation Agenda for All Reactor Generations

Materials for Sustainable Nuclear Energy: A European Strategic Research and Innovation Agenda for All Reactor Generations

Augmentation of heat transfer through passive techniques

Recent Advances in Computational Convective Heat Transfer Study in a Sub-Channel for Nuclear Power Reactor and Future Directions

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