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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Fusion Science and Technology
Latest News
Disa seeks NRC license for its uranium mine waste remediation tech
The Nuclear Regulatory Commission has received a license application from Disa Technologies to use high-pressure slurry ablation (HPSA) technology for remediating abandoned uranium mine waste at inactive mining sites. Disa’s headquartersin are Casper, Wyo.
U. Fischer, D. Leichtle, A. Serikov, P. Pereslavtsev, R. Villari
Fusion Science and Technology | Volume 64 | Number 3 | September 2013 | Pages 563-570
Nuclear Systems: Analysis and Experiments | Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 2) Nashville, Tennessee, August 27-31, 2012 | doi.org/10.13182/FST13-A19153
Articles are hosted by Taylor and Francis Online.
Several methodologies have been developed for the calculation of shut-down dose rates based on the use of the Monte Carlo (MC) technique for particle transport simulations including the rigorous two-step (R2S) approach and its recent R2Smesh extension, the direct one-step (D1S) method which employs one single MC transport simulation both for neutrons and decay gammas, and a rough rule of thumb (RoT) approximation based on neutron flux-to-dose conversion factors. The paper discusses these approaches and their applications to ITER with focus on dose rate estimations for the equatorial Test Blanket and Diagnostic Ports. These applications are complemented by benchmark analyses on shut-down dose rate measurements performed on JET showing the validity of the R2S and D1S approaches.