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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.
W. L. Pearl, E. G. Brush, G. G. Gaul, S. Leistikow
Nuclear Technology | Volume 3 | Number 7 | July 1967 | Pages 418-432
Technical Paper and Note | doi.org/10.13182/NT67-A27840
Articles are hosted by Taylor and Francis Online.
INCONEL alloy 625® fuel-cladding material has been corrosion-tested under heat-transfer conditions at metal temperatures up to 1500°F (816°C) in specially designed out-of-pile superheat facilities. The hydrogen and oxygen contents of the steam were controlled to simulate those found in boiling-water-reactor systems. The corrosion data from the 3600-h heat-transfer tests indicated good corrosion resistance up to the 1500°F metal temperature tested. A compositionally changed layer developed at the metal-oxide interface that appeared to reach a maximum depth at the higher temperatures. The heat-transfer test data indicated that except for a small buildup of oxide during the initial nonlinear transient corrosion period, most of the oxide formed in corrosion was carried downstream by the superheated steam. The uniform corrosion experienced by the INCONEL-625 when exposed isothermally to 1050 and 1150°F (566 and 621°C) for 10 000 h indicates an initially high-corrosion rate that decreases to a lower constant rate within the first 1000 h. A small proportion of the total oxide formed was gradually lost to the system.