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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Jan 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
February 2025
Nuclear Technology
January 2025
Fusion Science and Technology
Latest News
Reboot: Nuclear needs a success . . . anywhere
The media have gleefully resurrected the language of a past nuclear renaissance. Beyond the hype and PR, many people in the nuclear community are taking a more measured view of conditions that could lead to new construction: data center demand, the proliferation of new reactor designs and start-ups, and the sudden ascendance of nuclear energy as the power source everyone wants—or wants to talk about.
Once built, large nuclear reactors can provide clean power for at least 80 years—outlasting 10 to 20 presidential administrations. Smaller reactors can provide heat and power outputs tailored to an end user’s needs. With all the new attention, are we any closer to getting past persistent supply chain and workforce issues and building these new plants? And what will the election of Donald Trump to a second term as president mean for nuclear?
As usual, there are more questions than answers, and most come down to money. Several developers are engaging with the Nuclear Regulatory Commission or have already applied for a license, certification, or permit. But designs without paying customers won’t get built. So where are the customers, and what will it take for them to commit?
Josef Schaefer, Detlev Stöver, Rudolf Hecker
Nuclear Technology | Volume 66 | Number 3 | September 1984 | Pages 537-549
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-A33476
Articles are hosted by Taylor and Francis Online.
The phenomenon of hydrogen permeation through high-temperature alloys has been recognized as an important problem in developing nuclear energy production systems. Investigations are concerned with experimental techniques and requirements to conform with the concept of practical development. After establishing the data of hydrogen permeation through bare alloys, efforts are directed toward investigating the permeation behavior of surface oxidized walls. In this way 12 alloy types are examined under various conditions. The reduced penetration occurring under “process gas” atmosphere is determined by the “impeding factor”: It is the ratio of permeation rates measured under special conditions in the case of bare alloy annealed in pure hydrogen and in the case of its oxidized surface. One influence on the permeation behavior is proceeding from the metallic substrate of oxide coating: Centricast and wrought types of alloys are effective in different ways. Varied treatment before coating was significant only in the case of annealing in hydrogen. Most influential is the temperature acting upon both the permeating and the coating quality in a compensating manner. Temperature cycling in oxidizing atmosphere points to improved impeding. The relationship between the oxidation potential and the impeding conditions is not yet clear. In the temperature range between 650 and 900°C, a square root behavior below ∼5-bar hydrogen pressure is dominant, whereas a linear pressure dependence was detected above. A crossover range is obvious, especially distinct at higher temperatures. The influence of chromium oxide in the corrosion cover is manifested by metallurgical postexamination results corresponding with permeation data of selected samples.