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
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.
M. G. Stamatelatos, T. R. England
Nuclear Technology | Volume 45 | Number 3 | October 1979 | Pages 219-232
Technical Paper | Reactor | doi.org/10.13182/NT79-A32292
Articles are hosted by Taylor and Francis Online.
Delayed fission product beta and gamma decay spectra following short and long 235 U thermal-neutron irradiations and cooling times were calculated and compared with corresponding experimental results that have recently become available. These decay-heat source terms are of importance to nuclear reactor safety, particularly to loss-of-coolant accident analyses. The comparisons between calculations and experiments have shown that the state-of-the-art computational methods and the ENDF/B-IV-based nuclear data bases are generally adequate for 235U thermal fission product spectral source term calculations. These comparisons have also revealed some shortcomings in the data base for short-lived nuclides whose influence on the aggregate fission product spectra is mostly noticeable at very short cooling times.