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Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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AI at work: Southern Nuclear’s adoption of Copilot agents drives fleet forward
Southern Nuclear is leading the charge in artificial intelligence integration, with employee-developed applications driving efficiencies in maintenance, operations, safety, and performance.
The tools span all roles within the company, with thousands of documented uses throughout the fleet, including improved maintenance efficiency, risk awareness in maintenance activities, and better-informed decision-making. The data-intensive process of preparing for and executing maintenance operations is streamlined by leveraging AI to put the right information at the fingertips for maintenance leaders, planners, schedulers, engineers, and technicians.
L. M. Gaspar, D. A. Giordano, N. A. Greenfield, S. J. Kim, F. A. Kubic, M. R. Middlemas, A. J. Pizarro, W. J. Saeger, K. M. Sweetland, R. S. Reid
Nuclear Technology | Volume 209 | Number 1 | January 2023 | Pages S73-S91
Technical Paper | doi.org/10.1080/00295450.2021.1997540
Articles are hosted by Taylor and Francis Online.
The eBlock37 is a subscale electrically heated and heat-pipe-cooled prototype of a fast spectrum microreactor that is under development at Los Alamos National Laboratory. The prototype consists of an electrically heated core and gas-cooled heat exchanger. These subassemblies, both built from 316 L stainless steel, are thermally linked by an array of 37 sodium heat pipes that transfer a nominal 100 kW from the core at 700°C. An overarching objective of this effort is to overcome challenges associated with core block and heat exchanger manufacture and integration of high-temperature heat pipes into the assembly. Components that would be safety critical in an actual reactor, such as the heat pipe wicks, are being built under a Nuclear Quality Assurance 1 quality program. The completed assembly is intended for non-nuclear electrically heated testing, which will be conducted at a demonstration facility at Idaho National Laboratory. This paper provides a top-level summary of the efforts to date.