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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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!
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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.
A. I. Vedeneev et al.
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 43-46
Technical Paper | Tritium Science and Technology - Tritium Processing, Transportation, and Storage | doi.org/10.13182/FST05-A876
Articles are hosted by Taylor and Francis Online.
First experimental results of a tritium pellet injector steady-state operation is presented. The tritium injector TPI-1 was developed at the PELIN Laboratory and put in operation in Russian Federal Nuclear Center. It is a part of an experimental closed circuit for simulation of ITER fuel cycle. Results of several continuous extrusions of solid rod made of various hydrogen isotopes are presented. Transverse dimensions of an extruded ice rod with rectangular cross-section were ~ 3 × 4mm. The greatest extrusion velocity came to 15 mm/s for hydrogen and 9 mm/s for D-T mixture; tritium content in fuel mixture did not exceed 11%; pellet velocity ran up to 500 m/s at repetitive mode. An optimal mode of D-T ice extrusion was determined.
