Thermal conductivity correlation for uranium nitride fuel between 10 and 1923 K

Thermal conductivity of perspective fuel based on uranium nitride

“…The measured values of heat capacity of UN with oxygen content 0.13 wt.% and porosity of 12.4% and 15.6% TD were in the range (13.2-20.5) W/(m K) at temperatures from 295 to 1570 K. The thermal conductivity data obtained by the authors are in good agreement with the literature data received by Arai and Suzuki (1992), Ross and El-Genk (1988), Hayes et al (1990) and Bauer (1972) and can be described using expressions (2) and (3) (Fig. 1).…”

“…However, there is a wide variation in the data on uranium nitride thermal conductivity resulting from different measurement techniques and different fuel fabrication methods (typically resulting in different porosities and content of impurities) as demonstrated (Arai and Suzuki, 1992;Ross and El-Genk, 1988;Speidel and Keller, 1964;Enderbrock and Foster, 1964;Moore and Fulkerson, 1970;Hayes et al, 1965Hayes et al, , 1990Bauer, 1972;Taubin, 1986).…”

“…Based on the result of ten experimental work (Speidel and Keller, 1964;Enderbrock and Foster, 1964;Moore and Fulkerson, 1970;Hayes et al, 1965Hayes et al, , 1990Takahashi et al, 1971, Kikuchi andTakahashi, 1972;Ross and El-Genk (1988)) proposed the following expression for the thermal conductivity of uranium mononitride in the temperature range 298-1923 K with porosity 0-20% T:…”

“…Thus, the coefficient b is a function of temperature and depends on the type of porosity (open/closed) in the sample. Ross and El-Genk (1988) have recently shown that thermal conductivity correlation equation should take into account the fabrication methods and measurement techniques. To determine this dependence, the authors have measured the thermal conductivity of fuel obtained by three different methods (powder UN sintering, hot isostatic pressing, direct reaction of uranium and nitrogen arc melting) at temperatures 10-1923 K by DC and pulsed heating.…”

Modeling and Analysis of FCM UN TRISO Fuel Using the PARFUME Code

“…The UN thermal conductivity is obtained from nitride fuel properties (Ross 1988), and it is displayed in Appendix A. The fission gas release model for UN is detailed in Appendix A.…”