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
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
Jun 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
July 2025
Nuclear Technology
June 2025
Fusion Science and Technology
Latest News
NRC approves NuScale uprated SMR design
NuScale earned approval for its “larger” US460 77-MWe small modular reactor plant design, the Nuclear Regulatory Commission announced last week.
The standard design approval (SDA) is a determination by NRC staff that a reactor design meets the agency’s applicable design requirements, and companies can reference it when applying for a license to build and operate the reactor—but it does not ensure license approval from the commission.
Gee-Yong Park, Heung-Seop Eom, Seung Cheol Jang, Hyun Gook Kang
Nuclear Technology | Volume 183 | Number 1 | July 2013 | Pages 107-118
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT13-A16996
Articles are hosted by Taylor and Francis Online.
This paper describes a method of estimating the probability of failure for trip-functioning software of a fully digitalized reactor protection system. The Bayesian inference is used to estimate and update the probability of software failure along the software development life cycle. At the requirements and design phases, the probability of software failure is estimated from qualitative quality information based on a specific verification and validation process. This probability of failure is updated at the implementation/testing phases, based on the test data for trip functions implemented by software.
