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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
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
DOE opens pilot program to authorize test reactors outside national labs
Details of the plan to test new reactor concepts under the Department of Energy’s authority but outside national laboratory boundaries—first outlined in one of the four executive orders on nuclear energy released on May 23—were just released in a request for applications issued by the DOE.
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.
