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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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Nuclear Science and Engineering
June 2025
Nuclear Technology
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Latest News
Webinar: MC&A and safety in advanced reactors in focus
Towell
Russell
Prasad
The American Nuclear Society’s Nuclear Nonproliferation Policy Division recently hosted a webinar on updating material control and accounting (MC&A) and security regulations for the evolving field of advanced reactors.
Moderator Shikha Prasad (CEO, Srijan LLC) was joined by two presenters, John Russell and Lester Towell, who looked at how regulations that were historically developed for traditional light water reactors will apply to the next generation of nuclear technology and what changes need to be made.
13th Nuclear Plant Instrumentation, Control & Human-Machine Interface Technologies (NPIC&HMIT 2023)
Technical Session|Panel
Thursday, July 20, 2023|8:00–9:30AM EDT|301B
Session Chairs:
Ted Quinn (Paragon Energy Solutions)
Ian Jung (NRC)
Session Organizers:
The nuclear industry is pursuing the development and licensing of a number of advanced reactor designs of various types and sizes. Instrumentation and control for these designs can play a key role in the operation and safety of the facilities. Multiple designers are in various pre- or post-application licensing review stages working with the United States Nuclear Regulatory Commission (NRC). The NRC has also been preparing for the review of the licensing applications. One major area is to enhance the NRC’s regulatory infrastructure that includes the development of the rules and regulatory guidance better suited for the designs. The application of the risk-informed and performance-based (RIPB) approach is one of the most significant areas for the review of the designs. Some of the key examples are the ongoing 10 CFR Part 53 rulemaking effort, the issuance of Regulatory Guide (RG) 1.233, which endorses NEI 18-04, and Trial RG 1.247, which endorses the ASME/ANS non-LWR probabilistic risk assessment (PRA) standard, and the NRC’s ongoing advanced reactor content of application project (ARCAP) along with the industry’s technology-inclusive content of application project (TICAP) in NEI 21-07. The enhanced regulatory infrastructure affects, and can provide opportunities for, the instrumentation and control (I&C) design and licensing. Specific to I&C, the NRC staff has also issued Design Review Guide (DRG) for I&C to be ready for the advanced reactors, and several designers are using this guidance. This panel will discuss the NRC and industry perspectives on the development and licensing of advanced reactor I&C. The emphasis is placed on the I&C-related regulatory infrastructure, the I&C approaches of some of the designers, the industry implementation of such regulatory infrastructure, including the RIPB approach in RG 1.233 and DRG for I&C, and the potential or unique challenges in the I&C licensing.
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