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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
Proposed rule for more flexible licensing under Part 53 is open for comment
The Nuclear Regulatory Commission has published a proposed rule that has been almost five years in the making: Risk-Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors. The rule, which by law must take its final form before the end of 2027, would let the NRC and license applicants use technology-inclusive approaches and risk-informed, performance-based techniques to effectively license any nuclear technology. This is a departure from two licensing options with light water reactor–specific regulatory requirements that applicants can already choose.
R. C. Lloyd, S. W. Heaberlin, E. D. Clayton, R. D. Carter
Nuclear Technology | Volume 42 | Number 1 | January 1979 | Pages 13-21
Technical Paper | Reactor | doi.org/10.13182/NT79-A32158
Articles are hosted by Taylor and Francis Online.
A study was made of 100 violations of criticality safety specifications reported over a 10-yr period in the operations of fuel reprocessing plants. The seriousness of each rule violation was evaluated by assigning it a severity index value. The underlying causes, or reasons, for the violations were identified. A criticality event tree was constructed using the parameters, causes, and reasons found in the analysis of the infractions. The event tree provides a means for visualizing the paths to an accidental criticality. Some 65% of the violations were caused by misinterpretation on the part of the operator, being attributed to a lack of clarity in the specification and insufficient training; 33% were attributed to lack of care, whereas only 2% were caused by mechanical failure. A fault tree was constructed by assembling the events that could contribute to an accident. With suitable data on the probabilities of contributing events, the probability of the accident’s occurrence can be forecast. Estimated probabilities for criticality were made, based on the limited data available, that in this case indicate a minimum time span of 244 yr of plant operation per accident ranging up to ∼3000 yr subject to the various underlying assumptions made. Some general suggestions for improvement are formulated based on the cases studied. Although conclusions for other plants may differ in detail, the general method of analysis and the fault tree logic should prove applicable.