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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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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May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Deanna Jing Zhang, Dawnmathews Kalathiveettil (NRC)
Proceedings | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technolgies (NPIC&HMIT 2019) | Orlando, FL, February 9-14, 2019 | Pages 1114-1121
Modern digital instrumentation and controls (I&C) systems incorporate many design features that provide safety and reliability benefits to plant operations. However, design decisions relating to I&C system architecture and implementation of these design features may present challenges to demonstrating safety and compliance to regulatory requirements. There can be significant safety and regulatory impacts from design decisions related the I&C platform used, interfaces among redundant safety divisions and between safety and non-safety systems, deterministic behavior, and diversity strategies. These design decisions may influence the I&C system architecture, result in different hazards and hazard controls (e.g., measures for prevention or mitigation), and affect design complexity, all of which may necessitate corresponding levels of evidence (i.e., level of detail, analysis, testing, operating experience, etc.) to demonstrate that the I&C design provides reasonable assurance of safety and compliance with applicable regulatory requirements in an efficient and effective manner. This paper discusses some of the key design decisions for the APR1400 I&C system and architecture and their impact on the Nuclear Regulatory Commission (NRC) staff’s design certification application licensing review. For example, this paper discusses benefits and challenges associated with the I&C platform used for the safety-related I&C system. This paper also explores the challenges associated with non-safety to safety communications and the design constraints chosen that addressed hazards of concern associated with this communication and compliance with the independence design principle and regulatory requirement. In addition, this paper provides examples of information necessary to support the safety and regulatory compliance demonstration. Lastly, this paper provides additional insight on lessons learned during the regulatory process for the APR1400 I&C system design certification application review.