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
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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.
C. Z. Serpan, Jr., W. N. McElroy
Nuclear Technology | Volume 13 | Number 2 | February 1972 | Pages 185-193
Technical Paper | Material | doi.org/10.13182/NT72-A31053
Articles are hosted by Taylor and Francis Online.
Damage functions, represented here as multigroup cross sections for neutron-induced radiation damage production, were derived for irradiation of two A 350-series ferritic steels at temperatures of 510 and 430°F (266 and 221°C), representing the PM-2A and SM-1A reactor pressure vessels. The functions were derived using the SAND-II computer code with the neutron spectra and resulting increases in transition temperature from a series of irradiations in different reactor locations. The derived damage functions effected a best correlation of available data and on that basis are considered good through comparison of total fluence values determined both from experimental measurements and from the damage-function calculation technique. Trends are suggested for the magnitude of damage function cross-section values as a function of energy at low vs elevated temperatures. However, the present experimental data are not sufficiently definitive to draw positive conclusions about the specific contributions of neutrons of all energy levels to the neutron embrittlement process.