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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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Virginia utility considers SMRs
Dominion Energy Virginia has issued a request for proposals from leading nuclear companies to study the feasibility of putting a small modular reactor at its North Anna nuclear power plant.
While the utility says it is not a commitment to build an SMR at the site, the RFP is “an important first step in evaluating the technology and the North Anna site to support Dominion Energy customers’ future energy needs consistent with the company’s most recent Integrated Resource Plan.”
Glenn J. Neises, Terry J. Garrett
Nuclear Technology | Volume 93 | Number 1 | January 1991 | Pages 22-35
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT91-A34515
Articles are hosted by Taylor and Francis Online.
A steam line break transient is analyzed for the Wolf Creek Generating Station using RETRAN02/MOD3. The RETRAN analysis results and the modeling approaches used for the steam line break transient are described. The results of this analysis are compared with the results of the Wolf Creek Updated Safety Analysis Report (USAR). The steam line break results presented in the USAR comparison include mixing between the affected and unaffected loops in the reactor vessel, boron tracking in the reactor coolant system, and sensitivity studies of various parameters.