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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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
Fighting fatigue and maintaining 10 CFR Part 26 compliance
Fatigue has been identified as a major risk factor in industrial accidents. According to the National Safety Council, 13 percent of workplace injuries can be attributed to fatigue.1 Other research indicates that working 12 hours per day is associated with a staggering 37 percent increase in risk of injury.2 Considering fatigue was a contributing factor to major nuclear accidents at Chernobyl and Three Mile Island, it makes sense that the Nuclear Regulatory Commission imposes hefty fines to ensure strict adherence to its fatigue management regulations—particularly, Code of Federal Regulations Title 10, Part 26, “Fitness for Duty Programs.”
J. W. Allen, J. C. Robinson, N. J. Ackermann, Jr.
Nuclear Technology | Volume 22 | Number 3 | June 1974 | Pages 315-322
Technical Paper | Reactor | doi.org/10.13182/NT74-A31416
Articles are hosted by Taylor and Francis Online.
A study was made to determine the uncertainty in subcritical reactivity as inferred from inverse kinetics rod drop experiments (using the three-point method) due to the statistical uncertainty inherent in the observed count rate of the neutron sensor. The two methods employed were a classical propagation of error analysis, and an analysis of simulated repeated rod drops, with an assumption that the uncertainty in reactivity was due to the detection process itself for both techniques, To test the analysis methods, the reactivity uncertainties for various experimental rod drop data sets were computed by both methods. There was excellent agreement of the results. The propagation of error analysis may be used on three-point subcriticality measurements to provide an experimenter with an index to the statistical reliability of the inferred reactivity estimate.