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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Latest News
Securing the advanced reactor fleet
Physical protection accounts for a significant portion of a nuclear power plant’s operational costs. As the U.S. moves toward smaller and safer advanced reactors, similar protection strategies could prove cost prohibitive. For tomorrow’s small modular reactors and microreactors, security costs must remain appropriate to the size of the reactor for economical operation.
Y. L. Yuan, R. P. Gardner, K. Verghese
Nuclear Technology | Volume 77 | Number 1 | April 1987 | Pages 97-109
Technical Paper | Analyse | doi.org/10.13182/NT87-A33956
Articles are hosted by Taylor and Francis Online.
A Monte Carlo simulation model has been developed to predict the unscattered gamma-ray intensities of an in situ neutron capture prompt gamma-ray analysis system for assaying the elemental concentrations of material that move on a conveyor belt. The model incorporates all pertinent neutron and photon interactions for the assay of coal and all variance reduction techniques necessary to make every history a success. Prompt gamma-ray intensities from all elements of interest over a range of elemental compositions of the sample matrix are calculated in one execution of the program. The calculated results are verified with experimental results on a coal sample in a test configuration that is spiked with variable amounts of sulfur and titanium as two sample elements of interest. The model is expected to be very useful for the optimum design and calibration of on-line neutron capture prompt gamma-ray analysis systems operating in the conveyor belt geometry.