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Division Spotlight
Nuclear Nonproliferation Policy
The mission of the Nuclear Nonproliferation Policy Division (NNPD) is to promote the peaceful use of nuclear technology while simultaneously preventing the diversion and misuse of nuclear material and technology through appropriate safeguards and security, and promotion of nuclear nonproliferation policies. To achieve this mission, the objectives of the NNPD are to: Promote policy that discourages the proliferation of nuclear technology and material to inappropriate entities. Provide information to ANS members, the technical community at large, opinion leaders, and decision makers to improve their understanding of nuclear nonproliferation issues. Become a recognized technical resource on nuclear nonproliferation, safeguards, and security issues. Serve as the integration and coordination body for nuclear nonproliferation activities for the ANS. Work cooperatively with other ANS divisions to achieve these objective nonproliferation policies.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Construction begins on Kairos’s fluoride salt–cooled test reactor
Earlier today, on a site in Oak Ridge, Tenn., that was formerly home to the K-33 Gaseous Diffusion Plant, Kairos Power marked the start of construction on its low-power demonstration reactor. Named Hermes, the 35-MWt test reactor claims status as the first Gen IV reactor to be approved for construction by the Nuclear Regulatory Commission and the first non–light water reactor to be permitted in the United States in more than 50 years.
Dongxun Zhang, Wei Liu, Yuan Qian, Ji Que
Fusion Science and Technology | Volume 67 | Number 3 | April 2015 | Pages 681-684
Proceedings of TRITIUM 2013 | doi.org/10.13182/FST14-T109
Articles are hosted by Taylor and Francis Online.
Tritium was generated by the interaction of neutrons with the lithium and beryllium in the molten salt reactors (MSRs), which use Flibe as one of solvents of fluoride fuel. Tritium as by-product in the MSRs would be an important safety issue because it could easily diffuse through high temperature heat exchangers into environment. The experimental technique of gas driven permeation was used to investigate the transport parameter of hydrogen in Hastelloy C-276 which was considered as one of the candidate structure materials. The measurements were carried out at the temperature range of 400-800°C with hydrogen loading pressures ranging from 5×103 to 4×104 Pa. The H diffusive transport parameters for Hastelloy C-276 followed an Arrhenius law in this temperature range and were decreased due to the existence of the alloying elements compared with Ni201. The possible reason may be the trapping effects, which were formed by the alloying elements of Mo and Cr in the matrix. At the same time, the thin oxidation layer formed by the high Cr content could lead to the slower dissociation process of H2 at the surface.