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Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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Webinar: MC&A and safety in advanced reactors in focus
Towell
Russell
Prasad
The American Nuclear Society’s Nuclear Nonproliferation Policy Division recently hosted a webinar on updating material control and accounting (MC&A) and security regulations for the evolving field of advanced reactors.
Moderator Shikha Prasad (CEO, Srijan LLC) was joined by two presenters, John Russell and Lester Towell, who looked at how regulations that were historically developed for traditional light water reactors will apply to the next generation of nuclear technology and what changes need to be made.
Luciano Burgazzi
Nuclear Technology | Volume 156 | Number 2 | November 2006 | Pages 150-158
Technical Paper | Reactor Safety | doi.org/10.13182/NT06-A3781
Articles are hosted by Taylor and Francis Online.
The inclusion of passive safety-related systems within the advanced reactor design claims high system availability and reliability. A detailed system and safety analysis applying the failure mode and effect analysis (FMEA) approach is required as a primary step for the development of a methodology aimed at the reliability assessment of passive systems. The present study concerns thermal-hydraulic passive systems that are designed for decay heat removal and rely on natural circulation that foresee a heat exchanger immersed in a cooling pool. The main purposes of the work are to identify important accident initiators, find out the possible consequences to the plant deriving from component malfunctions, individuate possible causes, identify mitigating features and systems, and classify accident initiators in initiating events of accident sequences. A qualitative overview of accident sequences could be derived from the FMEA tables looking at consequences' description and preventive and corrective actions. Failure probabilistic evaluations are included as well to point out the probabilities and frequencies to have the plant in fault and/or unavailability conditions during passive system operation, therefore ensuring a complete set of initiating events of reactor accident sequences. Finally, important feedback to the design activities will derive from the FMEA study performed for safety assessment purposes. An important lesson elicited from the analysis is that measures against common-cause failures can reduce significantly the probability of failure of the system.