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
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Roger L. Clough, Kenneth T. Gillen
Nuclear Technology | Volume 59 | Number 2 | November 1982 | Pages 344-354
Technical Paper | Material | doi.org/10.13182/NT82-A33037
Articles are hosted by Taylor and Francis Online.
The deterioration of polyethylene and polyvinyl chloride cable materials in the containment building of an operating nuclear reactor has been investigated. Since the maximum dose experienced by the cable materials was only 2.5 Mrad during ∼12 yr of operating life, the extent of material degradation was surprising. Laboratory aging experiments on the two materials established that the cause of the material deterioration in the plant was radiation-induced oxidation. The degradation rate was correlated with local levels of radiation intensity. It was determined that strong synergisms of radiation and elevated temperature, and also dose-rate effects, lead to the surprisingly rapid degradation rates found with these materials. It is concluded that in the design of laboratory methods for aging and qualification testing of organic materials for use in a nuclear plant environment, the possible occurrence of dose-rate effects and synergisms needs to be taken into account.