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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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
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Industry Update—May 2025
Here is a recap of industry happenings from the recent past:
TerraPower’s Natrium reactor advances on several fronts
TerraPower has continued making aggressive progress in several areas for its under-construction Natrium Reactor Demonstration Project since the beginning of the year. Natrium is an advanced 345-MWe reactor that has liquid sodium as a coolant, improved fuel utilization, enhanced safety features, and an integrated energy storage system, allowing for a brief power output boost to 500-MWe if needed for grid resiliency. The company broke ground for its first Natrium plant in 2024 near a retiring coal plant in Kemmerer, Wyo.
B. John Garrick
Nuclear Technology | Volume 84 | Number 3 | March 1989 | Pages 319-330
Technical Paper | Probabilistic Safety Assessment and Risk Management / Nuclear Safety | doi.org/10.13182/NT89-A34216
Articles are hosted by Taylor and Francis Online.
In the short time that plant-specific, full-scope probabilistic risk assessments (PRAs) have been performed, extensive progress has been made in understanding and managing risk. After performing over 20 PRAs, one of the most impressive lessons learned is that quantitative risk management is tedious and hard work. It requires great attention to plant details and all the resources involved, including procedures, training, maintenance, quality control, staffing, engineering support, and, of course, a detailed knowledge of the plant, its systems, and the way they operate and interact with each other. It is clear that one of the greatest values of a comprehensive risk model is an increased understanding of the plant. Furthermore, that increased understanding is focused on the behavior of the plant under abnormal conditions. Those things important to risk are made visible and are prioritized. The basis exists to identify options for controlling risk in a systematic and logical way. The options can be evaluated not only in terms of the possible reduction in risk but also with respect to life-cycle costs and overall plant performance. One of the real challenges facing practitioners of quantitative risk assessment is to avoid undue emphasis on the numerical results. The numerical aspect of risk analysis should be viewed as a disciplining process, not as the end in itself The temptation to get into a “numbers game” is strong, and it should be resisted. The real emphases should be on exposing what is driving the risk and on taking specific actions to keep it under control; that is, the perspective ought to be one of risk management. Experience indicates that such an emphasis can result in enormous benefits. These results have impacted all aspects of nuclear plant safety, including training, regulatory compliance, preventive measures, maintenance prioritizing, spare parts, outage planning, and the basic decision-making process associated with power plant operations. The impact of plant-specific PRAs on traditional issues of safety has been major. Outstanding examples are large loss-of-coolant accidents (LOCAs), containment capacities, single-failure criteria, separate and independent safety trains, frontline safety system dependencies, system response requirements, system redundancy, the role of external events, and the role of selected support systems. Large LOCAs are not a major contributor to risk; most containment capacities greatly exceed their design basis; frontline safety systems are more dependent on support systems than previously believed; multiple failures are important contributors to risk; system response is sequence dependent; system redundancy is often not as important as system location and support system requirements; external events are often important contributors, especially to older plants; and support systems such as room ventilation are far more important to risk than perceived. Just as many lessons have been learned about nuclear plant risk through the application of quantitative risk assessment, there have also been many lessons learned about how to do risk assessments. Examples have to do with data handling, plant and system modeling, capturing the operator’s perspective, controlling the scope, transferring of technology, and achieving scrutability. There is still much room for improvement in all these and other areas. Yet, the progress toward real-time and continuous quantitative risk management has been extremely encouraging. The key is to have patience and not expect the process to be automatic.