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Division Spotlight
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.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Sungwhan Cho, Jin Jiang
Nuclear Technology | Volume 161 | Number 2 | February 2008 | Pages 98-107
Technical Paper | Reactor Safety | doi.org/10.13182/NT08-A3916
Articles are hosted by Taylor and Francis Online.
A new technique for analyzing the effect of testing on shutdown system (SDS) number 1 (SDS1) in Canadian deuterium uranium (CANDU) nuclear power plants is proposed. The effect of the test on the core damage probability is quantified using a Markov process model. The model is used to derive the effect of the test frequency on the unavailability and the spurious reactor trip probability. Two core damage scenarios are considered: one from a process failure with the unavailable SDS and the other from a spurious reactor trip. The Markov process model is then used with the core damage scenarios to analyze the effect of the test frequency on the core damage probability. The quantified core damage probabilities indicate that performing more frequent surveillance tests does not necessarily decrease the risk. In fact, there exists an optimal test frequency beyond which the probability of core damage starts to increase. This optimal test frequency is of significance in practice.