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 Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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.
William L. Daugherty, K. Linga Murty
Nuclear Technology | Volume 80 | Number 3 | March 1988 | Pages 443-450
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT88-A34068
Articles are hosted by Taylor and Francis Online.
X-ray diffraction techniques have been used to measure the texture of Zircaloy-4, which is described quantitatively by the crystallite orientation distribution function (CODF). Procedures for evaluating the anisotropy parameters in the modified Hill equation (R and P) from the CODF and their use in predicting creep behavior are reviewed. Alternatively, the same anisotropy parameters can be obtained from creep test data using appropriate mechanical deformation concepts. These R and P parameters are used to predict the creep behavior of fuel rod cladding both out of pile and in pile. The procedures involved in obtaining the anisotropy parameters from either crystallographic texture data or creep test data are summarized. These two approaches, previously discussed separately in the literature, are brought together for a direct comparison. Predictions of creep behavior based on texture measurements are compared with creep data. The utility of the anisotropy parameters in predicting postirradiation cladding dimensions is illustrated by reviewing the work of another research group. Excellent agreement between their model predictions and experimental results of postirradiation examination is observed.