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Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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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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Become a knowledge manager at UWC 2024
The American Nuclear Society is now accepting applications for knowledge managers to work during the 2024 Utility Working Conference and Vendor Technology Expo. This year’s UWC, “Nuclear Momentum: Advancing Our Clean Energy Future,” will be held August 4–7, 2024, at the JW Marriott Marco Island Beach Resort on Marco Island, Fla.=
Vinay Kumar, Lalit Singh, A. K. Tripathi
Nuclear Technology | Volume 197 | Number 1 | January 2017 | Pages 20-28
Technical Paper | doi.org/10.13182/NT16-89
Articles are hosted by Taylor and Francis Online.
Any risk in safety-critical or control applications may lead to catastrophic disaster; hence, safety is a primary concern for such applications. The impact of risk varies from minor inconvenience and cost to personal injury, significant economic loss, and death. Therefore, a safety assessment process should be an inherent part of the system development process to make a system safe or to ensure that the effects from failures are minimized. This paper deals with a new probabilistic approach to quantify the safety of safety-critical systems (SCSs) and control systems based on probabilistic safety assessment to deal with the shortcomings of the existing techniques. The methodology has been tested on 29 operational data sets to validate its effectiveness. This paper demonstrates the methodology on the digital feedwater controller system of a nuclear power plant. The results indicate that the method can identify possible hazards and quantify such hazards of a SCS.