ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
Meeting Spotlight
Nuclear and Emerging Technologies for Space (NETS 2025)
May 4–8, 2025
Huntsville, AL|Huntsville Marriott and the Space & Rocket Center
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
U.S. nuclear capacity factors: Stability and energy dominance
Nuclear generation has inertia. Massive spinning turbines keep electricity flowing during grid disturbances. But nuclear generation also has a kind of inertia that isn’t governed by the laws of motion.
Starting—and then finishing—a power reactor construction project requires significant upfront effort and money, but once built a reactor can run for decades. Capacity factors of U.S. reactors have remained near 90 percent since the turn of the century, but it took more than a decade of improvements to reach that steady state. The payoff for nuclear investments is long-term and reliable.
D. D. Lanning
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 565-574
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A32915
Articles are hosted by Taylor and Francis Online.
Thermally induced cracking of the UO2 fuel pellets undoubtedly results in some reduction of the effective fuel thermal conductivity, relative to that for solid UO2. This effect may be approximated by appropriately chosen “crack factors” that reduce the solid-UO2 thermal conductivity. We demonstrate that the assumption of reduced fuel conductivity always results in a reduction of the fuel stored energy that is inferred from fuel centerline temperature data. This reduction occurs whether the crack factors are introduced as simple constants or as functions of radial position within the fuel pellet. If fuel performance computer codes remain “tuned” to the current body of centerline temperature data, those codes will predict lower fuel stored energy when fuel cracking is taken into account regardless of the modeling assumptions invoked. Accounting for fuel cracking should lead to a reduction in calculated peak cladding temperatures obtained in some loss-of-coolant accident simulations.