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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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Latest News
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.
D. A. Gall, E. F. Doyle, J. G. Bourne
Nuclear Technology | Volume 2 | Number 3 | June 1966 | Pages 226-230
Technical Paper and Note | doi.org/10.13182/NT66-A27591
Articles are hosted by Taylor and Francis Online.
A prototype device to control the exit steam quality in the individual fuel element assemblies of a boiling water reactor was designed, constructed and tested at simulated reactor operating conditions. The device consists of two Venturis and a mechanism for comparing the pressure signals from the Venturis and controlling the flow by means of a hydraulically operated valve. The device, which is completely self-contained within one channel of a boiling water reactor, held the discharge volume quality to ± 6% of the design value during transients in the heat transfer rate of up to 25%. The addition of the device to the high heat flux channels of a boiling water reactor would permit designing reactors at a higher heat flux for the same departure from nucleate boiling. The pressure across the core (header to header) is increased by ≈ 20% for a reactor of the Dresden type. Overall economic effects on reactor operations, including reactivity effects, were not evaluated.