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
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
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.
John R. Phillips
Nuclear Technology | Volume 28 | Number 2 | February 1976 | Pages 282-290
Technical Paper | Technique | doi.org/10.13182/NT76-A31569
Articles are hosted by Taylor and Francis Online.
The method for the nondestructive determination of two-dimensional radial isotopic distributions of fission and activation products of irradiated fuel pins was improved. In this method the fuel pins are gamma-scanned diametrally at two or more angular orientations, and the diametral isotopic scans are unfolded into two-dimensional radial isotopic distributions. The computer code for processing the data was improved so that it calculates the individual diametral volume segments, the source self-attenuation factors, and the source intensity matrices. The two-dimensional source intensity matrices are presented as radial isotopic distributions, density plots, contour plots, and isometric projections. The new computer code improves the precision and reduces the analysis time as shown in the examination of more than 10 experimental fast-reactor fuel pins.
