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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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.
W. R. Martin, J. R. Weir
Nuclear Technology | Volume 1 | Number 5 | October 1965 | Pages 478-483
Technical Paper | doi.org/10.13182/NT65-A20559
Articles are hosted by Taylor and Francis Online.
The ductility of irradiated structural alloys is of concern in reactor design. The purpose of this study is to determine some of the parameters affecting such ductility. Type-304 stainless steel has been thus investigated up to 600°C. In general, the ductility of stainless steel, solution annealed prior to irradiation, is better than steel cold worked prior to irradiation. One exception to this generality occurs under the conditions of irradiation followed by straining at 200°C, where low ductility is observed for irradiated stainless steel, solution annealed prior to irradiation. Cold working followed by carbide precipitation at an intermediate temperature improves the ductility of irradiated stainless steel at 200°C.