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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.
Nguyen Thuy (EdF R&D)
Proceedings | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technolgies (NPIC&HMIT 2019) | Orlando, FL, February 9-14, 2019 | Pages 377-386
Complexity, safety relevance and long life time make nuclear power plants heavily dependent on information and skilled people. The knowledge accumulated during design, construction and operation is a critical asset that must be preserved for continuous improvement and future modifications. This paper proposes an approach that supports the safety and reliability of nuclear power plants based on cross-disciplinary methods and tools to create, maintain and exploit a structured knowledge basis for long-term operation, maintenance and up-grade. It proposes advanced modelling and justification methods to capture design information that currently often remains incompletely documented. In particular, it aims at making safety properties, dependencies and reasons behind design solutions understandable to all stakeholders. As a step towards its vision of model-based knowledge repositories, it extends traditional system descriptions with assumptions, operational constraints, design rationales and safety justifications. The knowledge base also links design solutions to requirements in regulations and standards. In addition, advanced plant models enable use of computer tools e.g. for automated dependency analysis and simulation. Focusing on design models for plant operation, the approach works in a multidisciplinary fashion and looks at reactor islands as socio-technical systems. Within the context of knowledge management and organizational learning, it integrates process and plant engineering, instrumentation and control system design and human factors engineering. On the basis of the current state-of-the-art and industrial needs, a common framework is defined. The general principles are refined towards more formal modelling languages and software tools. Finally, the framework and its implementations are tested in industrial case studies, and the experiences are used to refine the outputs of the project.