ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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!
Latest Magazine Issues
Jul 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
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.