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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!
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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.
Masaki Kitagawa, Hiroshi Hattori, Akira Ohtomo, Tetsuo Teramae, Junichi Hamanaka, Hiroshi Ukikusa
Nuclear Technology | Volume 66 | Number 3 | September 1984 | Pages 675-684
H. Design Codes and Life Prediction | Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material | doi.org/10.13182/NT84-A33489
Articles are hosted by Taylor and Francis Online.
A design guide for high-temperature gas-cooled reactor components is proposed and applied to the design and construction of the l.5-MW(thermal) helium heat exchanger test loop for nuclear steelmaking. To assure that the design method covers all conceivable failure modes and has a large enough safety margin, a series of lifetime tests of partial model may be needed. For this project, three types of model tests are performed. A lifetime test of an in-scale model of the center manifold pipe and eight heat exchanger tubes is described. Applied load is the combination of the simulated thermal expansion stress (deformation controlled quantity) and primary stress by internal pressure of tubes. The level of both loads is much higher than the corresponding values in the actual plant, which causes failure of the model in a shorter time. The eight tubes are arranged so that each is subjected to different damage conditions. The lifetime tests ran for 48 days, and six tubes out of eight failed during the test at the highest stressed stub tubes. Other parts of the components were found to be sound after the test. A damage criterion with a set of material constants and a simplified method for stress-strain analysis for a stub tube under a three-dimensional load are newly developed and used to predict the lives of each tube. The predicted lives are compared with the experimental lives and good agreement is found. The lifetime test model is evaluated according to the proposed design guide, and it is found that the guide has a safety factor of ∼200 in life for this particular model.