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2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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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Latest News
BWRX-300 SMR passes U.K. regulatory milestone
GE Vernova Hitachi Nuclear Energy’s BWRX-300 small modular reactor has completed the second step of the generic design assessment (GDA) process in the United Kingdom. In this step, the U.K. Office for Nuclear Regulation, the Environment Agency, and Natural Resources Wales did not identify “any fundamental safety, security safeguard or environmental protection shortfalls with the design of the BWRX-300.” Step 1 was completed in December 2024.
Truong V. Vo, Doyle R. Edwards
Nuclear Technology | Volume 106 | Number 1 | April 1994 | Pages 110-124
Technical Paper | Reactor Operation | doi.org/10.13182/NT94-A34953
Articles are hosted by Taylor and Francis Online.
The multiyear program entitled Nondestructive Evaluation Reliability for In-Service Inspection of Light Water Reactors, sponsored by the U.S. Nuclear Regulatory Commission, is being conducted at the Pacific Northwest Laboratory. The goals of the program are to determine the reliability of current in-service inspection of pressure boundary systems and components and to develop recommendations that can ensure a suitably high inspection reliability. The long-term objective is to develop recommendations for improved in-service inspections. In meeting program objectives, a risk-based method has been developed to guide the development of inspection plans. The method uses results of probabilistic risk assessment and failure modes and effects analysis techniques to identify and prioritize the most risk-important systems and components for inspection at nuclear power plants. The Surry Nuclear Power Station Unit I was selected for demonstrating the methodology. The specific system addressed in this study was the high-pressure injection/recirculation (HPI/R) system. The results provide a risk-based ranking of components within the HPI/R system, which can be used to guide the development of improved inspection plans for nuclear power plants. This work will subsequently be used in supporting the revisions of the American Society of Mechanical Engineers’ codes and standards.