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. W. Mahoney, N. E. Paton
Nuclear Technology | Volume 23 | Number 1 | July 1974 | Pages 53-62
Technical Paper | Material | doi.org/10.13182/NT74-A31433
Articles are hosted by Taylor and Francis Online.
The effects of carbide precipitation and carbon content on crack propagation rates in Type 316 stainless steel were determined for the temperature range of -196 to 649°C. It was shown that neither carbon content nor carbide precipitation had any recordable effect on crack propagation rates for the range of parameters investigated. Fatigue life, however, has been shown by other investigators to be a function of both carbon content and carbide distribution. These results provide evidence for a hypothesis that crack initiation is sensitive to carbon content and morphology in Type 316 stainless steel, whereas crack propagation rate is not. A good correlation was obtained between macroscopic crack growth rate and striation spacing measurements.