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
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
Latest News
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
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.