A Simplified Mechanistic Approach for Modeling Thermal Conductivity of Metallic Nuclear Fuels

2019 ◽  
Author(s):  
T. Pavlov

Author(s):  
Jayangani I. Ranasinghe ◽  
Ericmoore Jossou ◽  
Linu Malakkal ◽  
Barbara Szpunar ◽  
Jerzy A. Szpunar

The understanding of the radial distribution of temperature in a fuel pellet, under normal operation and accident conditions, is important for a safe operation of a nuclear reactor. Therefore, in this study, we have solved the steady-state heat conduction equation, to analyze the temperature profiles of a 12 mm diameter cylindrical dispersed nuclear fuels of U3O8-Al, U3Si2-Al, and UN-Al operating at 597 °C. Moreover, we have also derived the thermal conductivity correlations as a function of temperature for U3Si2, uranium mononitride (UN), and Al. To evaluate the thermal conductivity correlations of U3Si2, UN, and Al, we have used density functional theory (DFT) as incorporated in the Quantum ESPRESSO (QE) along with other codes such as Phonopy, ShengBTE, EPW (electron-phonon coupling adopting Wannier functions), and BoltzTraP (Boltzmann transport properties). However, for U3O8, we utilized the thermal conductivity correlation proposed by Pillai et al. Furthermore, the effective thermal conductivity of dispersed fuels with 5, 10, 15, 30, and 50 vol %, respectively of dispersed fuel particle densities over the temperature range of 27–627 °C was evaluated by Bruggman model. Additionally, the temperature profiles and temperature gradient profiles of the dispersed fuels were evaluated by solving the steady-state heat conduction equation by using Maple code. This study not only predicts a reduction in the centerline temperature and temperature gradient in dispersed fuels but also reveals the maximum concentration of fissile material (U3O8, U3Si2, and UN) that can be incorporated in the Al matrix without the centerline melting. Furthermore, these predictions enable the experimental scientists in selecting an appropriate dispersion fuel with a lower risk of fuel melting and fuel cracking.



2018 ◽  
Vol 39 (5) ◽  
pp. 714-723 ◽  
Author(s):  
Y. Lu ◽  
Q. Q. Tang ◽  
C. P. Wang ◽  
Z. S. Li ◽  
Y. H. Guo ◽  
...  


2018 ◽  
Author(s):  
Alex Resnick ◽  
Katherine Mitchell ◽  
Jungkyu Park ◽  
Hannah Maier ◽  
Eduardo B. Farfán ◽  
...  

The present study employs a molecular dynamics simulation to explore thermal transport in various oxide nuclear fuels with defects such as uranium oxide and plutonium oxide. In particular, the effect of vacancy and substitutional defects on the thermal transport in actinide oxides are investigated. It is found that the thermal conductivities of these oxide nuclear fuels are significantly reduced by the presence of vacancy defects. In spite of their small size, oxygen vacancy is shown to alter the thermal conductivity of oxide fuels greatly; 0.1% oxygen vacancy reduces the thermal conductivity of plutonium dioxide by more than 10% when the number of unit cell in length is 100. It was shown that the missing of larger atoms alters the thermal conductivity of actinide oxides more significantly. For the case of uranium dioxide, 0.1% uranium vacancies decrease the thermal conductivity by 24.6% while the same concentration of oxygen vacancies decreases the thermal conductivity of uranium dioxide by 19.4%. However, the uranium substitutional defects are shown to have a minimal effect on the thermal conductivity of plutonium dioxide because of the small change in the atomic mass.



1973 ◽  
Vol 46 (3) ◽  
pp. 253-258 ◽  
Author(s):  
G. Ondracek ◽  
B. Schulz


2016 ◽  
Vol 31 (7) ◽  
pp. 1480-1489 ◽  
Author(s):  
Abhijit Saha ◽  
Sadhan Bijoy Deb ◽  
Manoj Kumar Saxena

Development of a common analytical methodology for the determination of trace impurities in U–Ti, U–Zr and U–Mo alloy fuels by inductively coupled plasma mass spectrometry.





2013 ◽  
Vol 440 (1-3) ◽  
pp. 580-585 ◽  
Author(s):  
Taku Matsumoto ◽  
Tatsumi Arima ◽  
Yaohiro Inagaki ◽  
Kazuya Idemitsu ◽  
Masato Kato ◽  
...  




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