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
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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!
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Nuclear Science and Engineering
February 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Ontario eyes new nuclear development
A 1,300-acre site left undeveloped on the shores of Lake Ontario four decades ago could see new life as the home to a large nuclear facility.
Bogdan Florian Monea, Eusebiu Ilarian Ionete, Catalin Ducu, Stefan Ionut Spiridon, Sorin Moga, Xingbo Han, Wei Liu
Fusion Science and Technology | Volume 77 | Number 5 | July 2021 | Pages 382-390
Technical Paper | doi.org/10.1080/15361055.2021.1903782
Articles are hosted by Taylor and Francis Online.
In the present study, the effect of Hf and Ti substitution of Zr in the ZrCo alloy, used for hydrogen isotope storage, has been investigated in order to ascertain the improvement of the anti-disproportionation property of ZrCo hydrides. The ultimate goal of the investigation is to develop a safe and economically viable solution for the long-term storage of deuterium and tritium. The intermetallic compounds Zrl-xTixCo and Zrl-xHfxCo (x = 0.1, 0.2) were prepared and their suitability for hydrogen isotope storage, protium (H) and deuterium (D), was investigated. The alloys were synthesized by arc melting under a controlled argon atmosphere and characterized by scanning electron microscope and X-ray diffraction analysis. The hydrogen isotope storage behavior of these alloys was probed by loading and unloading protium and deuterium. We present the pressure, composition, and temperature measurements for desorption, together with the thermodynamic parameters (enthalpy and entropy) of these alloys. The experimental results show that Ti and Hf substitution in the ZrCo alloys is suitable for fast delivery of hydrogen isotopes, even after their long-term storage.
