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
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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!
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Latest News
NRC updating GEIS rule for new nuclear technology
The Nuclear Regulatory Agency is issuing a proposed generic environmental impact statement (GEIS) for use in reviewing applications for new nuclear reactors.
In an April 17 memo, NRC secretary Carrie Safford wrote that the commission approved NRC staff’s recommendation to publish in the Federal Register a proposed rule amending 10 CFR Part 51, “Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions.”
Truong V. Vo, Bryan F. Gore, Elizabeth J. Eschbach, Fredric A. Simonen
Nuclear Technology | Volume 88 | Number 1 | October 1989 | Pages 13-20
Technical Paper | Fission Reactor | doi.org/10.13182/NT89-A34332
Articles are hosted by Taylor and Francis Online.
Some of the goals of the Nondestructive Evaluation Reliability Program sponsored by the U.S. Nuclear Regulatory Commission at Pacific Northwest Laboratory are to assess current inspection requirements for all pressure boundary systems and components, to determine whether improvements to the requirements are needed, and, if necessary, to develop recommendations for revising the American Society of Mechanical Engineers Boiler and Pressure Vessel Code and regulatory requirements. Part of the work performed in addressing this goal was the development and demonstration of a method to establish in-service inspection priorities through the use of probabilistic risk assessment (PRA) results. The Oconee-3 PRA and the observed weld failure data of the nuclear plants operating in the United States are used to identify and prioritize the most risk-important systems for inspection. Failure modes and effects analysis methodology is then used to identify and prioritize the most riskimportant piping sections of the Oconee-3 emergency feedwater system. Based on the results of this study, this method is demonstrated to be a useful tool for identifying systems and piping sections or welds that need to be inspected.