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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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
A more open future for nuclear research
A growing number of institutional, national, and funder mandates are requiring researchers to make their published work immediately publicly accessible, through either open repositories or open access (OA) publications. In addition, both private and public funders are developing policies, such as those from the Office of Science and Technology Policy and the European Commission, that ask researchers to make publicly available at the time of publication as much of their underlying data and other materials as possible. These, combined with movement in the scientific community toward embracing open science principles (seen, for example, in the dramatic rise of preprint servers like arXiv), demonstrate a need for a different kind of publishing outlet.
E. G. Estochen, J. E. Klein
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 79-82
Technical Paper | Tritium Science and Technology - Tritium Processing, Transportation, and Storage | doi.org/10.13182/FST48-79
Articles are hosted by Taylor and Francis Online.
A 38 cm (15 inch) long metal hydride bed fabricated using 11.4 cm (4.5 inch) O.D., standard schedule 316/316L stainless steel pipe was fitted with 22 strain gauges to measure tangential and longitudinal stress resulting from hydride absorption and desorption cycling. Tests were conducted using two different LaNi4.25Al0.75 metal hydride fill-levels in the bed.Tests conducted with hydride filled to two-thirds (1.75L) of the 2.63L total bed volume resulted in a maximum stress less than one-third of the pipe's ASME Code allowable, for hydride absorption up to a hydrogen-to-metal ratio (H/M) of 0.86. After 15 absorption/desorption tests and hydride passivation, examination of the bed interior revealed a significant decrease in particle size and increase in hydride height. The second fill level had 0.4L of fresh hydride added to the bed's cycled hydride material, and 56 absorption/desorption tests, up to a gas loading of 0.83 H/M performed. Second fill tests resulted in maximum stresses less than 40% of the ASME Code allowable. Post-test bed radiographs showed a further increase in the apparent hydride fill height, and internal component deformation.