Abstract

Nuclear fuel pellets are sintered in high-temperature furnaces in an atmosphere with strictly defined requirements for the composition of the gas environments in the furnace’s different temperature zones. The preset process conditions in the mixed nitride uranium-plutonium (MNUP) fuel pellet sintering furnace is achieved through the respective gas supply arrangement and by the design of the barriers between the temperature zones and that of the gas supply and discharge units. A CFD model was created in the Ansys Fluent package and validated for testing the functionality of the design concepts used to develop the MNUP fuel sintering furnace channel. A mockup of the sintering furnace channel, which makes a part of the gas-dynamic test bench, was developed and fabricated for the analytical model validation.The paper presents a description of the test bench design and performance for measuring the concentration of gases in the channel simulating the nitride nuclear fuel sintering furnace channel. The results of the test bench gas-dynamic studies were used for the computational and experimental justification of the approaches used to develop the sintering furnace channel. The functionality of the barriers for the sintering furnace channel division into zones with the preset composition of the gas environments and the gas supply and discharge units has been tested experimentally. The obtained experimental data on the distribution of the process gas concentration makes it possible to validate computational thermophysical and gas-dynamic CFD models of the MNUP fuel sintering furnace channel.

Highlights

  • Research ArticleTest bench for gas-dynamic studies in the furnace channel for nuclear fuel pellet sintering*

  • An advanced nuclear fuel type for fast neutron reactors is the so-called dense fuel having a density higher than that of uranium dioxide (UO2) used predominantly at the present time

  • New designs have been proposed to ensure the preset composition of the gas environment in the temperature zones of the Mixed nitride uranium-plutonium (MNUP) fuel pellet sintering channel

Read more

Summary

Research Article

Test bench for gas-dynamic studies in the furnace channel for nuclear fuel pellet sintering*. Academic editor: Yury Korovin ♦ Received 1 March 2019 ♦ Accepted 23 May 2019 ♦ Published 21 June 2019

Introduction
Conclusions
Full Text
Paper version not known

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