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.
Explore membership for yourself or for your organization.
Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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
Oct 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
November 2025
Nuclear Technology
October 2025
Fusion Science and Technology
Latest News
OECD NEA meeting focuses on irradiation experiments
Members of the OECD Nuclear Energy Agency’s Second Framework for Irradiation Experiments (FIDES-II) joint undertaking gathered from September 29 to October 3 in Ketchum, Idaho, for the technical advisory group and governing board meetings hosted by Idaho National Laboratory. The FIDES-II Framework aims to ensure and foster competences in experimental nuclear fuel and structural materials in-reactor experiments through a diverse set of Joint Experimental Programs (JEEPs).
Truong V. Vo, Michael S. Harris, Bryan F. Gore
Nuclear Technology | Volume 84 | Number 1 | January 1989 | Pages 14-22
Technical Paper | Fission Reactor | doi.org/10.13182/NT89-A34192
Articles are hosted by Taylor and Francis Online.
Probabilistic risk assessment (PRA) based inspection guidance has been developed using information from the PRA for Arkansas Nuclear One Unit 1 (ANO-1). This information will be used in conjunction with the U.S. Nuclear Regulatory Commission (NRC) Inspection and Enforcement Manual and has been prepared in the form of a plant-specific appendix for incorporation into this manual. An analytical method was developed for calculating risk importance for affected plant systems. This was used to prioritize the ANO-1 plant systems using the Fussel- Vesely importance measure on the basis of core melt probability. System fault trees were reanalyzed to identify and rank the risk significant components in each system. The product of this effort is a prioritized listing of systems and components associated with 98% of the inspectable portion of the risk from ANO-1. This compilation will subsequently be used by NRC inspectors in the preparation of inspection plans addressing risk-important systems and components at the ANO-1 power plant.