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Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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.
J. L. Straalsund, M. M. Paxton
Nuclear Technology | Volume 13 | Number 1 | January 1972 | Pages 99-102
Technical Note | Material | doi.org/10.13182/NT72-A31072
Articles are hosted by Taylor and Francis Online.
Densification occurs during the aging of austenitic stainless steels. This study was conducted to determine the extent of densification during thermal aging of AISI Type 316 stainless steel. This objective was accomplished through both length change measurements and bulk density measurements on Type 316 stainless-steel tubing before and after aging treatments at 1200°F for aging times up to 1000 h. Various cold work levels, from 0 to 20%, were investigated. In all cases the tubes were found to shrink, the shrinkage increasing with cold-work level and aging time with a maximum change of −0.06% ΔL/L. A comparison of the bulk density and length change measurements indicates that within the experimental accuracy the densification phenomena are isotropic. Irradiation-induced creep and swelling in austenitic stainless steels have been a source of major concern in the development of LMFBRs. The densification or shrinkage phenomena influence measurements particularly for low values of strain and/or swelling. It is therefore important to take the densification phenomena into account when extrapolating low fluence data on swelling and creep.
