ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
Latest Magazine Issues
Jul 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
David A. Rehbein, Roger W. Carlson
Nuclear Technology | Volume 31 | Number 3 | December 1976 | Pages 348-356
Technical Paper | Fuel | doi.org/10.13182/NT76-A31671
Articles are hosted by Taylor and Francis Online.
Many thermal-hydraulic computer codes employ a fuel rod heat transfer model to couple the fuel rod temperatures with the hydraulic driving forces. Frequently, these models utilize uniform thermal conductivity for the fuel to reduce computer usage and storage. To evaluate the effect of this modeling, the uniform thermal conductivity model in COBRA III was modified to incorporate temperature-dependent thermal conductivity utilizing the complete expansion of the gradient of the heat flux, including the term that represents the gradient of the thermal conductivity. Demonstrative calculations for two transients showed that the peak fuel temperatures are very dependent upon the nonuniformity of the thermal conductivity. However, the peak cladding temperatures are almost independent of modeling of the thermal conductivity of the fuel because the clad temperatures are determined by the clad properties and the total amount of heat being transferred from the fuel to the coolant. The heat transferred is proportional to the integral of the thermal conductivity, which is virtually independent of the specific dependence of the temperature dependence of the thermal conductivity. The intermediate approach that employs the correct thermal conductivity at each point in the calculation but ignores the term in the heat conduction equation that accounts for the variation in the thermal conductivity was shown to yield results that are very similar to the uniform thermal conductivity cases. It is concluded that a uniform thermal conductivity model is adequate for models that are intended for the analysis of transients where the limiting constraint is the peak cladding temperature, such as the loss-of-coolant accident. However, models that are intended for the analysis of transients where the peak fuel temperature is limiting should employ the temperature dependence of the thermal conductivity.