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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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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.
Hubertus Nickel, Philip J. Ennis, Florian Schubert, Hans Schuster
Nuclear Technology | Volume 58 | Number 1 | July 1982 | Pages 90-106
Technical Paper | Material | doi.org/10.13182/NT82-A32962
Articles are hosted by Taylor and Francis Online.
As in conventional high temperature technology, the qualification of metallic materials for high temperature reactor (HTR) applications is based on creep behavior, fatigue properties, corrosion resistance, and thermal stability. Of specific interest are the effects of the primary coolant helium, which contains trace impurities of hydrogen, methane, carbon monoxide, and water vapor, on mechanical behavior. In addition, irradiation effects on the properties of absorber rod cladding and tritium permeation from the primary coolant into the process gas are important areas for investigation. The results show that, for test times of up to 20 000 h, the creep-rupture strength in air and in HTR helium lies in the same scatter band. The results of low cycle fatigue tests indicate a beneficial effect of HTR helium on the cycles of failure. Investigations of corrosion in HTR helium have shown that acceptable corrosion resistance can be achieved by strict control of the impurity content of the helium. Using the available creep-rupture data and the linear damage accumulation rule, the acceptable service lives of intermediate heat exchanger tubes were calculated for Inconel alloy 617 at 950°C. The data that are being accumulated from the various test programs will form the basis of a design code for nuclear components operating at temperatures >800 °C.