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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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
Nuclear moratoriums crumble around the world
The recent surge in positive sentiment about nuclear as the most viable answer to global energy needs and decarbonization goals has found governments around the world taking steps to reverse course on decades-old bans, moratoriums, and restrictions on new nuclear development.
Anastasios Mironidis, Leon Lidofsky, George Grochowski, Lefteris Tsoukalas
Nuclear Technology | Volume 127 | Number 2 | August 1999 | Pages 170-185
Technical Paper | Reactor Operations and Control | doi.org/10.13182/NT99-A2993
Articles are hosted by Taylor and Francis Online.
The problem of core damage severity evaluation during a core-threatening accident of a pressurized water reactor is addressed. An expert system, Core Damage Evaluator (CoDE), is developed that makes an adept utilization of the inferring capabilities of fuzzy logic to classify the core in the damage severity category: "intact," "clad failure," or "core melt" or a combination of the last two. If it is determined that some form of core damage exists, the logic model enters a quantification stage to provide a numerical assessment of the damage.The model is provided with two row vector inputs at a rate of 100 to 150 vector pairs per minute. The qualitative vector consists of 69 elements, whereas the quantitative one contains 83. These elements constitute instantaneous physical parameter values provided by the plant instrumentation. The inferencing procedure employed in this problem is the generalized modus ponens (GMP), which has its origin in the field of approximate reasoning.