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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
Can hydrogen be the transportation fuel in an otherwise nuclear economy?
Let’s face it: The global economy should be powered primarily by nuclear power. And it probably will by the end of this century, with a still-significant assist from renewables and hydro. Once nuclear systems are dominant, the costs come down to where gas is now; and when carbon emissions are reduced to a small portion of their present state, it will become obvious that most other sources are only good in niche settings. I mean, why use small modular reactors to load-follow when they can just produce that power instead of buffering it?
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.