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
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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.
Martin A. Molecke, James A. Ruppen, Ronald B. Diegle
Nuclear Technology | Volume 63 | Number 3 | December 1983 | Pages 476-506
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT83-A33274
Articles are hosted by Taylor and Francis Online.
Studies on the corrosion and mechanical behavior of TiCode-12 and other titanium alloys to be used as candidate canister or overpack barriers in a high-level waste (HLW) repository or test facility in salt have been in progress at Sandia National Laboratories since 1976. Titanium alloys were selected as the primary materials for detailed testing based on candidate screening analyses (general corrosion and economic assessments) of ∼20 different alloys. The corrosion behavior of TiCode-12 has been evaluated as a function of: brine composition, temperature, time, pH, oxygen concentration, and gamma radiolysis. Uniform corrosion rates are in the range of 0.1 to 10 µm/yr; no significant pitting or crevice corrosion has been observed. This can be compared to the long-term measured rate of 0.13 mm/yr for ductile cast iron in Brine A, analyzed as a corrosion-allowance canister material. The highly adherent, passivating titanium oxide film that provides the corrosion protection has been evaluated via electrochemical polarization and surface analysis techniques to enable modeling of the corrosion mechanism(s). An increase in the corrosion rate by a factor of ∼2 was observed for sensitized TiCode-12; the rate appears to be modified by the Ti2Ni intermetallic phase and iron impurity content. Alterations in the composition and processing procedure of TiCode-12 have been evaluated to optimize corrosion, mechanical, and mill-producibility properties for HLW package applications. Slow strain rate testing of TiCode-12 revealed no apparent susceptibility to stress corrosion cracking; no significant changes in tensile properties were observed, but alterations in fracture mode were determined to be caused by internal hydrogen content. Some embrittlement occurs at hydrogen concentrations in the range of 200 to 300 ppm by weight (wppm), but the macroscopic mechanical properties of TiCode-12 are not significantly affected at concentrations up to 1100 wppm. Further research on slow crack growth threshold stress intensity as a function of hydrogen content is required before any hydrogen content limit can be imposed. Based on the analysis of available corrosion and metallurgical results, an all-TiCode-12 HLW canister package for use in a repository or test facility in salt is being proposed. Such a simplified HLW canister could provide long-term containment integrity and significantly minimize total HLW isolation system costs when compared to other waste package design concepts.