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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Latest News
Optimizing Maintenance Strategies in Power Generation: Embracing Predictive and Preventive Approaches
In the high-stakes world of power generation, ensuring continuous operation and reducing downtime are central priorities. With the increasing complexity of power generation systems, maintenance practices are evolving to meet these demands more efficiently. Understanding the roles of Predictive Maintenance (PdM), Preventive Maintenance (PM), and Reactive Maintenance (Run-to-Failure) is crucial for maintenance professionals in the energy sector to make informed decisions about equipment management and long-term operational strategy.
C. Parisi, E. Negrenti, M. Pecchia
Nuclear Science and Engineering | Volume 178 | Number 4 | December 2014 | Pages 524-538
Technical Paper | doi.org/10.13182/NSE14-40
Articles are hosted by Taylor and Francis Online.
This paper summarizes the evaluation for core I and core VIII of the Babcock & Wilcox Spectral Shift Control Reactor critical experiment program. The Spectral Shift Control Reactor concept, moderated and cooled by a variable mixture of heavy and light water, envisaged changing of the thermal neutron spectrum during the operation to encourage breeding and to sustain the core criticality. Core I contained 484 fuel rods with 4% UO2 fuel in light water while core VIII contained 2188 fuel rods with 93% enriched UO2-ThO2 fuel in a moderator mixture of heavy and light water. For core I, the criticality experiment and measurements of the thermal disadvantage factor were evaluated. For core VIII, only the criticality experiment was evaluated. For both cores, experimental uncertainties were determined confirming the good level of accuracy achieved by the experimentalists. Based on the experimental configurations, benchmarks were proposed, and their biases were determined.