ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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!
Latest Magazine Issues
May 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
June 2024
Nuclear Technology
Fusion Science and Technology
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.
Tunc Aldemir, Don W. Miller, Michael Stovsky, Jason Kirschenbaum, Paolo Bucci, L. Anthony Mangan, Audeen Fentiman, Steven A. Arndt
Nuclear Technology | Volume 159 | Number 2 | August 2007 | Pages 167-191
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT07-A3863
Articles are hosted by Taylor and Francis Online.
Nuclear power plants are in the process of replacing the existing analog instrumentation and control (I&C) systems with digital technology. Digital systems distinguish themselves from other control and instrumentation systems mainly due to the presence of active software/firmware as well as hardware. The U.S. Nuclear Regulatory Commission policy statement on the use of probabilistic risk assessment (PRA) methods in nuclear regulatory activities encourages licensees to use PRA and associated analyses to support the licensing applications to the extent supported by the state-of-the-art and data. Before digital system reviews can be performed in a risk-informed manner, PRAs will need the capability to model digital I&C systems. The available methodologies for the reliability and risk modeling of digital I&C systems are reviewed with respect to their capability to account for the features of the digital I&C systems relevant to digital reactor protection and control systems, as well as the integrability of the resulting model into an existing PRA. It is concluded that the methodologies that rank as the top two with most positive features and least negative or uncertain features (using subjective criteria based on reported experience) are the dynamic flowgraph methodology and the Markov methodology combined with the cell-to-cell mapping technique, each with different advantages and limitations.