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Division Spotlight
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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.”
Alireza Haghighat, Ramana Veerasingam
Nuclear Technology | Volume 101 | Number 2 | February 1993 | Pages 237-243
Technical Note | Material | doi.org/10.13182/NT93-A34785
Articles are hosted by Taylor and Francis Online.
Several neutron cross-section libraries used for fluence calculations at the reactor pressure vessel (RPV) based on one-dimensional SN transport calculations are analyzed. It is demonstrated that the BUGLE-80, SAILOR, and ELXSIR libraries yield similar results, while the CASK library predicts significantly different results through and beyond the RPV. The use of the revised ENDF/B- V iron cross sections yields a significant increase in the neutron fluxes beyond the ironcontaining regions. This result has direct impact on the reactor cavity dosimetry that is being considered for the RPV fluence estimation.