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
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
Teruya Tanaka, Takeo Muroga, Akio Sagara
Fusion Science and Technology | Volume 47 | Number 3 | April 2005 | Pages 530-534
Technical Paper | Fusion Energy - First Wall, Blanket, and Shield | doi.org/10.13182/FST05-A738
Articles are hosted by Taylor and Francis Online.
Compatibility between tritium self-sufficiency and neutron shielding performance of self-cooled liquid blanket systems without solid neutron multiplier was investigated for the purpose of application to the conceptual helical reactor design of modified FFHR2 having the blanket space of 120 cm. The results of the neutronics calculation indicated that all of the Li/V-alloy, Flibe/V-alloy and Flibe/JLF-1 (Reduced Activation Ferritic steel) blankets are feasible for tritium breeding ability and neutron shielding performance. With the use of vanadium alloys, operation efficiency will be enhanced.
