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Division Spotlight
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.
Meeting Spotlight
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
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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Disney World should have gone nuclear
There is extra significance to the American Nuclear Society holding its annual meeting in Orlando, Florida, this past week. That’s because in 1967, the state of Florida passed a law allowing Disney World to build a nuclear power plant.
Anton Andrashov (Radics LLC), Ievgenii Bakhmach (Research and Production Corporation Radiy), Vyacheslav Kharchenko, Andriy Kovalenko, (Centre for Safety Infrastructure-Oriented Research and Analysis)
Proceedings | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technolgies (NPIC&HMIT 2019) | Orlando, FL, February 9-14, 2019 | Pages 327-335
The paper summarizes approaches and successful Equipment Qualification process performed in the scope of RadICS FPGA-based platform certification under US Nuclear Regulatory Commission (NRC) requirements. Such equipment was represented by a test specimen, built on Field-Programmable Gate Array (FPGA)-based RadICS Platform, which was previously certified under IEC 61508 to meet Safety Integrity Level (SIL) 3 requirements. Design and development processes of the test specimen were under recently developed 10 CFR 50 Appendix B Quality Management System. The paper also describes the general strategy of US NRC certification and an approach to Equipment Qualification, including preparation to Equipment Qualification, types of equipment used in Equipment Qualification process, configuration of the equipment, general plan of the Equipment Qualification process, as well as description for the external factors. Comprehensive statistics and lessons learned for the performed Equipment Qualification process, as well as appropriate results are presented. Moreover, the scope of subsequent audit, performed by US NRC representatives, is discussed.