Abstract

The steam generator in a nuclear power plant is a type of heat exchanger in which heat transfer occurs from the hot fluid in multiple channels to the cold fluid. Therefore, a uniform flow over multiple channels is necessary to improve heat exchanger efficiency. The study aims at experimentally investigating the improvement of flow uniformity by the perforated plate in the heat exchanger used for a sodium-cooled fast reactor stream generator. A 1/4-scale experimental model for one heat exchanger unit with 33 × 66 channels was manufactured. The working fluid was water. A perforated plate was systematically designed using numerical simulations to improve the flow uniformity over the 33 × 66 channels. As a result, the flow uniformity greatly improved at a slight cost of pressure drop. To validate the numerical results, planar particle image velocimetry measurements were performed on the selected planes in the inlet and outlet headers. The experimental velocity profiles near the exits of the channels were compared with numerical simulation data. The experimental profiles agreed with the numerical data well. Both the numerical simulation and the experimental results showed a slight increase in pressure drop, despite significant improvement in the flow uniformity.

Highlights

  • The overall flow pattern was of interest; the particle image velocimetry (PIV) measurements were conducted for the entire inlet header region

  • A perforated plate was designed to improve the flow uniformity in a heat exchanger used in an sodium-cooled fast reactor (SFR) steam generator

  • To experimentally validate the improvement of the flow uniformity, the PIV technique was applied to water flow in the heat exchanger unit

Read more

Summary

Introduction

Publisher’s Note: MDPI stays neutral with regard to jurisdictional claims in published maps and institutional affiliations. A sodium-cooled fast reactor (SFR) is a fast neutron nuclear reactor cooled by liquid sodium. One of the primary advantages is an efficient utilization of uranium resources and a reduction of a high-level waste volume and toxicity. The main disadvantage is the possibility of large heat and hydrogen generation if sodium comes into contact with water. Because the benefits outweigh the disadvantages, the Generation IV International Forum selected the SFR as one of the advanced nuclear energy systems, the Generation IV reactors [1]. The SFR was evaluated as the most advanced and feasible system [2]

Methods
Results
Discussion
Conclusion
Full Text
Published version (Free)

Talk to us

Join us for a 30 min session where you can share your feedback and ask us any queries you have

Schedule a call