Test bench for gas-dynamic studies in the furnace channel for nuclear fuel pellet sintering *
-
Published:2019-06-21
Issue:2
Volume:5
Page:171-175
-
ISSN:2452-3038
-
Container-title:Nuclear Energy and Technology
-
language:
-
Short-container-title:NUCET
Author:
Kuzmin Ilya V.,Leshchenko Anton Yu.,Pavlov Sergey V.,Shamsutdinov Rinat N.,Mochalov Yuriy S.
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.
Publisher
Pensoft Publishers
Reference20 articles.
1. A comparative study into the advantages and disadvantages of using metal and mixed nitride uranium-plutonium fuel in fast reactors. Izvestiya Rossiyskoy akademii nauk.;Adamov;Energetika,2015
2. Fabrication of (U, Pu)N fuel pellets