ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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Nuclear Science and Engineering
August 2024
Nuclear Technology
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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.
D. R. Duncan
Nuclear Technology | Volume 39 | Number 2 | July 1978 | Pages 199-206
Technical Paper | Material | doi.org/10.13182/NT78-A32078
Articles are hosted by Taylor and Francis Online.
Creep rates of metals can be greatly enhanced by neutron irradiation experienced in a fast reactor en vironment. Because irradiation-induced creep strains can be large in magnitude for duct and cladding components, the effect of irradiation creep on subsequent mechanical property behavior must be quantified to provide a design base for core component performance assessment. Pressurized tubes that had sustained a peak value of irradiation creep strain of 1.04% and peak fast fluences of 10 X 1022 n/cm2 under irradiation in the Experimental Breeder Reactor II from 650 to 857 K were tested in subsequent transient burst loading. Results of testing show that subsequent deformation, is unaffected by prior irradiation creep within experimental error.
