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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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.”
Gregory J. Van Tuyle, Gregory C. Slovik, Robert J. Kennett, Bing C. Chan, Arnold L. Aronson
Nuclear Technology | Volume 91 | Number 2 | August 1990 | Pages 165-184
Technical Paper | Safety of Next Generation Power Reactor / Nuclear Saftey | doi.org/10.13182/NT90-A34426
Articles are hosted by Taylor and Francis Online.
Analytical results from an independent evaluation of the so-called “inherent reactor shutdown” mechanism in the proposed Power Reactor Inherently Safe Module (PRISM) advanced liquid-metal reactor design are discussed. Inherent reactor shutdown, in this context, refers to the tendency of the metal fuel reactor to inherently transition to a low power level when the reactor overheats significantly. Such behavior was demonstrated at the small Experimental Breeder Reactor II in 1986, but extrapolation to the proposed PRISM design concept requires extensive computer calculations. Analyses by Brookhaven National Laboratory (BNL) tend to confirm calculations submitted by General Electric (GE) and the Argonne National Laboratory staff providing technical expertise to GE on the metal fuel. The BNL calculations also indicate some problem areas, particularly with respect to very low probability events that could lead to sodium voiding.