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Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Latest News
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
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.