ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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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Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Muyi Ni, Qunying Huang, Yong Song, Xiaoqiang Chen
Fusion Science and Technology | Volume 60 | Number 3 | October 2011 | Pages 1125-1128
Concept and Facility | Proceedings of the Ninth International Conference on Tritium Science and Technology | doi.org/10.13182/FST11-A12613
Articles are hosted by Taylor and Francis Online.
A tritium analysis model for the fusion-based hydrogen production reactor FDS-III blanket system was developed, including the High Temperature Liquid (HTL) blanket and major components of the auxiliary system (such as TES, CPS, and HX etc.). Based on the model, tritium safety assessment on HTL blanket system was done by using the Tritium Analysis Software (TAS), in which various factors affecting tritium permeation were considered,. The results showed that most of the tritium released into the environment would permeate through the heat exchanger as HTO. And a reasonable compromise among the various requirements could be found to keep the tritium released from HTL blanket system under safety guide line, based on the fabrication technology of the He/H2O heat exchanger, the capability of vent detritiation system, etc.