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.
J. S. Armijo, J. R. Low, U. E. Wolff
Nuclear Technology | Volume 1 | Number 5 | October 1965 | Pages 462-477
Technical Paper | doi.org/10.13182/NT65-A20558
Articles are hosted by Taylor and Francis Online.
The mechanical properties and microstructures of Type-304 stainless steel were studied as a function of cold work, neutron irradiation, and testing temperature. True-stress, true-strain tensile tests were made on nonirradiated specimens at 70°F (21°C), 600°F (315°C), and 1300°F (700°C), and on irradiated specimens at 70°F and 600°F. Specimens were irradiated to 1.25 x 1020 n/cm2 (>1 MeV) at 110°F (43°C). Neutron irradiation increased the yield strength and ultimate tensile strength of annealed and cold-worked specimens at 70° F and at 600° F. The incremental increase in these properties decreased with increasing cold work. The elongation of nonirradiated and irradiated specimens tested at 70° F was found to increase with initial levels of cold work and then to decrease. This effect was not observed at 600° F. The most severe decreases in mechanical stability were observed in heavily deformed (greater than 20% reduction in thickness) and irradiated specimens tested at 600° F. These specimens failed in a ductile manner with total elongations as low as 1/2%. The increases in the strength and decreases in plastic stability produced by irradiation were combined by measuring the energy absorbed to plastic instability (area under the true-stress, true-strain curve up to the point of maximum load). This energy value was found to be an effective method for comparing the effects of the various variables. Cold work was found to produce large amounts of austenite-to-martensite transformation. Neutron irradiation was found to produce no measurable increase in martensite content. Transmission electron microscopy of irradiated specimens confirmed the presence of martensite and epsilon phase in Type-304 stainless steel. Irradiated specimens contained high concentrations of black dots which were not observed in nonirradiated specimens. In some instances these black dots could be resolved into loops. These black dots are presumed to be clusters of vacancies or interstitials produced by neutron radiation.