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Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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.
Thomas J. Marciniak
Nuclear Technology | Volume 8 | Number 5 | May 1970 | Pages 401-416
Paper | Reactor | doi.org/10.13182/NT70-A28685
Articles are hosted by Taylor and Francis Online.
A simple, stable, time-optimal digital control program has been developed with general application to zero- or low-power nuclear reactors for power-level changes, especially power increases. The program is required to increase the power level while maintaining a minimum allowed period, and to reach the demand power with little or no overshoot. A switching criterion was derived using a discrete version of the Pontryagin Maximum Principle. The switch point was found to be dependent upon the minimum allowed period and the maximum reactivity removal rate of the controlled regulating rod. The control program developed was applied to digital simulation of three reactor models and was adapted for use on the Argonne Thermal Source Reactor (ATSR) for power-level changes. The maximum overshoot experienced was ∼1% for various minimum allowed reactor periods and reactivity removal rates.