Scaling methodologies and similarity analysis for thermal hydraulics test facility development for water-cooled small modular reactor

Bhowmik, P.K.; Sabharwall, P.; Johnson, J.T.; Retamales, M.E.T.; Wang, C.; O'Brien, J.E.; Lietwiler, C.; Wu, Q.

doi:10.1016/j.nucengdes.2024.113235

Nuclear Engineering and Design

2024

DOI: 10.1016/j.nucengdes.2024.113235

|View full text |Cite

Scaling methodologies and similarity analysis for thermal hydraulics test facility development for water-cooled small modular reactor

P.K. Bhowmik,

P. Sabharwall,

J.T. Johnson

et al.

Help me understand this report

Search citation statements

Order By: Relevance

Paper Sections

Select...

Citation Types

Supporting

Mentioning

Contrasting

Year Published

2024

Publication Types

Select...

Article3

Relationship

Self Cite0

Independent3

Authors

Journals

Cited by 3 publications

References 67 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

Scaling design and similarity analysis of a floating nuclear power plant

Liu,

Wang,

Deng

et al. 2024

Nuclear Engineering and Design

View full text Add to dashboard Cite

Scaling design and similarity analysis of a floating nuclear power plant

Liu,

Wang,

Deng

et al. 2024

Nuclear Engineering and Design

View full text Add to dashboard Cite

Method for Calculating Heat Transfer in a Heat Accumulator Using a Phase Change Material with Intensification Due to Longitudinal Fins

Lebedev,

Deev,

Deev

2024

Energies

View full text Add to dashboard Cite

One of the challenges in energy supply for isolated power systems is maintaining a steady balance between generated and consumed energy. The application of energy storage systems and flexible energy sources is the most preferable approach for these systems. Small- and medium-sized nuclear power plants are promising, carbon-free options for energy supply to isolated power systems. However, these plants have low maneuverability. To solve this problem, this article discusses the use of a thermal accumulator using a phase change material (solar salt) to heat feedwater. Tubes with longitudinal fins are used to intensify heat transfer in the storage system. This paper presents a method for calculating heat transfer along the entire heat exchange surface of such an accumulator. A series of 2D simulations were conducted to study the solidification process of solar salt around a heat exchange tube at various temperatures on the inner wall surface. The regression dependences of heat transfer on the temperature of the inner surface of the wall and the thickness of the solid PCM layer were determined. Using the presented method and the obtained regression dependencies, we determined the time graphs of the temperature change in the heat transfer fluid at the outlet of the accumulator during discharge. Based on the results presented, it was found that an accumulator with 72.7 tons of solar salt (dimensions: 6 × 3.71 × 2.15 m) can replace a high-pressure heater №1 at a low-power nuclear power plant (50 MW) during 3450 s.

show abstract

Modeling and Visualization of Coolant Flow in a Fuel Rod Bundle of a Small Modular Reactor

Dmitriev,

Demkina,

Dobrov

et al. 2024

Fluids

View full text Add to dashboard Cite

This article presents the results of an experimental study of the coolant flow in a fuel rod bundle of a nuclear reactor fuel assembly of a small modular reactor for a small ground-based nuclear power plant. The aim of the work is to experimentally determine the hydrodynamic characteristics of the coolant flow in a fuel rod bundle of a fuel assembly. For this purpose, experimental studies were conducted in an aerodynamic model that included simulators of fuel elements, burnable absorber rods, spacer grids, a central displacer, and stiffening corners. During the experiments, the water coolant flow was modeled using airflow based on the theory of hydrodynamic similarity. The studies were conducted using the pneumometric method and the contrast agent injection method. The flow structure was visualized by contour plots of axial and tangential velocity, as well as the distribution of the contrast agent. During the experiments, the features of the axial flow were identified, and the structure of the cross-flows of the coolant was determined. The database obtained during the experiments can be used to validate CFD programs, refine the methods of thermal-hydraulic calculation of nuclear reactor cores, and also to justify the design of fuel assemblies.

show abstract

scite is a Brooklyn-based organization that helps researchers better discover and understand research articles through Smart Citations–citations that display the context of the citation and describe whether the article provides supporting or contrasting evidence. scite is used by students and researchers from around the world and is funded in part by the National Science Foundation and the National Institute on Drug Abuse of the National Institutes of Health.

Contact Info

customersupport@researchsolutions.com

10624 S. Eastern Ave., Ste. A-614

Henderson, NV 89052, USA

This site is protected by reCAPTCHA and the Google Privacy Policy and Terms of Service apply.

Blog Terms and Conditions API Terms Privacy Policy Contact Cookie Preferences Do Not Sell or Share My Personal Information

Made with 💙 for researchers

Part of the Research Solutions Family.

Scaling methodologies and similarity analysis for thermal hydraulics test facility development for water-cooled small modular reactor

Cited by 3 publications

References 67 publications

Scaling design and similarity analysis of a floating nuclear power plant

Scaling design and similarity analysis of a floating nuclear power plant

Method for Calculating Heat Transfer in a Heat Accumulator Using a Phase Change Material with Intensification Due to Longitudinal Fins

Modeling and Visualization of Coolant Flow in a Fuel Rod Bundle of a Small Modular Reactor

Contact Info

Product

Resources

About