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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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NRC v. Texas: Supreme Court weighs challenge to NRC authority in spent fuel storage case
The State of Texas has not one but two ongoing federal court challenges to the Nuclear Regulatory Commission that could, if successful, turn decades of NRC regulations, precedent, and case law on its head.
K. Goldmann, N. Hyman, S. Kostman, J. McKee
Nuclear Technology | Volume 3 | Number 2 | February 1967 | Pages 117-126
Technical Paper and Note | doi.org/10.13182/NT67-A27809
Articles are hosted by Taylor and Francis Online.
Data are presented on carbon and nitrogen transfer by potassium in 16 stainless-steel thermal convection loops containing Cb-1%Zr and stainless-steel tabs. Typical test conditions were 5000 h at 1600°F maximum, 1200°F minimum. Changes in weight, composition, and microstructure of both tab materials were determined as a function of time over the full temperature range. Changes in loop wall composition, microstructure, and tensile properties were determined at the end of the test. The Cb-1%Zr formed thin carbide and nitride surface films at a rate limited by diffusion through the films rather than by availability of carbon and nitrogen in the potassium. Cold bend tests showed good ductility in Cb-1%Zr after 5000 h. Transfer of carbon and nitrogen from hot to cold stainless steel was unaffected by the Cb-1%Zr and had less effect on tensile properties than microstructural changes associated with the thermal history.