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.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Feb 2026
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
March 2026
Nuclear Technology
February 2026
Fusion Science and Technology
January 2026
Latest News
Fusion energy: Progress, partnerships, and the path to deployment
Over the past decade, fusion energy has moved decisively from scientific aspiration toward a credible pathway to a new energy technology. Thanks to long-term federal support, we have significantly advanced our fundamental understanding of plasma physics—the behavior of the superheated gases at the heart of fusion devices. This knowledge will enable the creation and control of fusion fuel under conditions required for future power plants. Our progress is exemplified by breakthroughs at the National Ignition Facility and the Joint European Torus.
Kunihiko Tsuchiya, Hideki Imaizumi, Hiroshi Kawamura, Rokuro Oyamada, Toshiyuki Kabutomori, Yuichi Wakisaka
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1431-1436
Tritium Storage, Distribution, and Transportation | Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30613
Articles are hosted by Taylor and Francis Online.
An in-situ irradiation test of a fusion blanket is planned in JMTR (Japan Materials Testing Reactor) using lithium containing ceramics as the tritium breeder and beryllium as the neutron multiplier. Therefore, it is necessary to develop getters for the recovery of the tritium gas. In this study, Zr9Ni11 alloy was chosen as a getter, and pressure-composition isotherms between 20°C and 300°C, and other properties were measured for its application. The breakthrough test of hydrogen was carried out with Ar+H2 gas. The evaluation of the examined getter materials leads to the conclusion that the Zr9Ni11 alloy may be used for the in-situ irradiation test of fusion blanket.