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
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.
Hans Huschka, Guenther Luthardt, Volker E. Portscher
Nuclear Technology | Volume 66 | Number 3 | September 1984 | Pages 562-569
F. Hydrogen and Tritium Permeation | Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material | doi.org/10.13182/NT84-A33478
Articles are hosted by Taylor and Francis Online.
One crucial point of the prototype nuclear process heat is the permeation of hydrogen isotopes through the walls of the heat exchanger materials. The in situ growth of oxide layers provides an effective barrier against hydrogen permeation. Basic investigations with a large scope of heat-resistant alloys have been carried out by Kernforschungsanlage (KFA) Jülich. Further research has been done by NUKEM and Maschinenfabrik Augsburg-Nürnberg, Neue Technologie, to develop superior coatings that are effective from reactor startup. The NUKEM procedure is a simple and cost-efficient method. It comprises oxidation of the disk-shaped metal samples in excess steam (with or without addition of other gases) at elevated temperatures in a once-through manner. Adjustments of various parameters are being made to work out the conditions for optimal quality of the oxides on several alloys. Evaluation is based on permeation measurements with deuterium in the Deuperm facility of KFA. In some cases, tritium permeability was determined at the University of Münster. Backup information is provided by scanning electron microscope analysis, diffractometry, and microprobe examination. First coating experiments with steam/air yielded duplex scales consisting of an inner oxide, which is mainly Cr2O3 and an outer layer of the spinel type containing iron, nickel, and chromium, as well as some manganese throughout the scale. A compositional shift toward chromium oxide monolayers obtained with oxidation in steam correlates with improved permeation properties. Their quality depends strongly on various parameters of the procedure, which are currently being optimized. These are chiefly surface grinding, recrystallization annealing, and possibly thermocycling. For Hastelloy-X, best results are obtained with steam oxidation at 1000°C. Until now, permeability has been reduced by a factor of several hundred with disk specimens. Postoxidation by means of process gas exposure at Rheinbraun further increased the factor to over one thousand, the same as with tube specimens in Auwarm. The adherence to the metal matrix is excellent throughout; no spalling has been observed.