Nanofluid Thermal Management in Nuclear Reactor Systems

Efficient removal of heat from the reactor core is fundamental to safe and economical nuclear power plant operation. Nanofluids—suspensions of engineered nanoparticles in a conventional coolant such as water—have attracted considerable interest for their capacity to augment thermal conductivity and convective heat transfer coefficients. By exploiting materials with high intrinsic thermal conductivity (for example aluminium oxide, copper oxide or graphene nanoplatelets), nanofluids can increase the Nusselt number at a given flow rate and reduce temperature gradients within fuel assemblies. Such enhancements may permit higher power densities, more compact core designs or enhanced safety margins against departure from nucleate boiling. Advances in synthesis, surface functionalisation and stability assessment under irradiation have addressed early concerns over sedimentation, corrosion and particle agglomeration. Complementary developments in computational fluid dynamics (CFD) and neutronic modelling now enable integrated evaluation of thermal–hydraulic and reactivity feedback effects. Practical demonstrations in subchannel and full-scale loop tests have begun to validate predicted gains in heat removal and peak cladding temperature reduction. Ongoing challenges include ensuring long-term particulate stability under high gamma flux, mitigating erosion of structural components and assessing the impact of nanoparticle additives on reactor coolant chemistry.

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Nanofluid Thermal Management in Nuclear Reactor Systems publication trend

The graph below shows the total number of articles in nanofluid thermal management in nuclear reactor systems across all publications each year (not limited to Nature Index journals).

Technical terms

Nanofluid: A base fluid containing suspended nanoparticles to enhance thermal properties.

Nusselt number: A dimensionless measure of convective heat transfer relative to conduction across a fluid layer.

Reynolds number: A dimensionless parameter characterising flow regime by comparing inertial and viscous forces.

Departure from nucleate boiling ratio: The margin between operating heat flux and the onset of film boiling in a coolant channel.

Computational fluid dynamics: Numerical methods and algorithms used to analyse fluid flow and heat transfer.

References

1. Enhancing Thermal–Hydraulic Performance in Nuclear Reactor Subchannels with Al2O3 Nanofluids: A CFD Analysis. Energies (2024).
2. Exploring thermal flow dynamics in pressurized water reactors using hybrid graphene nanoplatelet coolants. Energy Science & Engineering (2024).
3. Neutronic study for the dual use of nanofluid as a primary coolant and neutron absorber in VVER-1000 nuclear power reactor. Journal of Physics Conference Series (2018).