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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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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
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.
Doo-Hyung Choe, Jae-Hyuk Baeg, Suk-Hwn Jung (Doosan Heavy Industries & Construction), Steve Yang (Doosan HF Controls Corp.)
Proceedings | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technolgies (NPIC&HMIT 2019) | Orlando, FL, February 9-14, 2019 | Pages 367-376
Rod Control System (RCS) is to control position of the neutron absorbing full-length rods (control rods or rods) in Nuclear Power Plants (NPPs). Although an RCS is classified as non-safety system, there is stringent requirement for its reliability and availability to avoid an unwanted reactor trip due to a single failure of the RCS. The unwanted reactor trip caused by a single failure of the RCS refers to Single Point Vulnerability (SPV) of the RCS, which is detrimental to an NPP’s continuous and healthy operations because of significant economic impact including operation & maintenance cost. Therefore, it is important to design and implement an RCS with high reliability, availability, operability, and maintainability that can tolerate faults and defeat the SPV for NPPs. For this reason, a modern and highly reliable RCS has been developed with the goal of reducing the SPV to zero and by applying disciplined specification and implementation of design as well as comprehensive Equipment Qualification (EQ) that are consistent with the 10 CFR50 Appendix B requirements. In the modernized RCS, full redundancy controller is used in both the logic and power cabinets. The other key improvements for this modernized RCS are the adoption of dual grippers (versus a single gripper used in the old RCS) and application of DC-hold function (not implemented in the old RCS). These design and implementation aims at completely eliminating the SPV and is fulfilled through analyzing 300 SPV cases in the operating history of the old RCS, which used non-redundant control components.