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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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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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Latest News
ARG-US Remote Monitoring Systems: Use Cases and Applications in Nuclear Facilities and During Transportation
As highlighted in the Spring 2024 issue of Radwaste Solutions, researchers at the Department of Energy’s Argonne National Laboratory are developing and deploying ARG-US—meaning “Watchful Guardian”—remote monitoring systems technologies to enhance the safety, security, and safeguards (3S) of packages of nuclear and other radioactive material during storage, transportation, and disposal.
Mei-Ya Wang, Tsung-Kuang Yeh
Nuclear Science and Engineering | Volume 186 | Number 2 | May 2017 | Pages 180-189
Technical Paper | doi.org/10.1080/00295639.2016.1273014
Articles are hosted by Taylor and Francis Online.
Hydrogen water chemistry (HWC), aiming at coolant chemistry improvement, has been adopted worldwide for mitigating intergranular stress corrosion cracking in operating boiling water reactors (BWRs). However, a conventional hydrogen injection system employed in this technology was designed to operate only at power levels >30% of the rated power or at coolant temperatures >232°C. This system is usually in an idle and standby mode during a start-up operation. The coolant in a BWR during a cold shutdown normally contains a relatively high level of dissolved oxygen from intrusion of atmospheric air. Accordingly, the structural materials in the primary coolant circuit (PCC) of a BWR could be exposed to a strongly oxidizing environment for a short period of time during a subsequent start-up operation. In this study, the computer code DEMACE was used to investigate the variations in redox species concentration and in electrochemical corrosion potential (ECP) of structural components in the PCC of a domestic BWR during start-up operations with HWC. Simulations were carried out for power levels ranging from 3.8% to 11.3% during start-up operations. Our analyses indicated that for selected power levels with steam present in the core, a higher power level would tend to promote a more oxidizing coolant environment and therefore lead to less HWC effectiveness on ECP reduction. At even lower power levels in the absence of steam, the effectiveness of HWC was more prominent. At a feedwater hydrogen concentration of merely 0.1 parts per million, significant ECP reductions in the PCC of the BWR were observed.