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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Full slate of candidates for 2025 ANS leadership positions
At the end of 2024, the candidates for the annual American Nuclear Society election were announced. Since then, Catherine Prat, an ANS member since 2012, launched a successful write-in campaign to be considered for a seat on the Board of Directors. Having received at least 200 signatures from Society members in favor of her nomination, Prat is now a candidate by petition, bringing the total number on the ballot to 18 candidates who have been nominated for the positions of ANS vice president/president-elect, treasurer, and six board positions (four U.S. directors, one non-U.S. director, and one student director). Ballots will be sent via email on Tuesday, March 4, 2025, and must be submitted by 1:00 p.m. (EDT) on Tuesday, April 15, 2025.
D. Petti, R. Hill, J. Gehin, H. Gougar, G. Strydom, T. O’Connor, F. Heidet, J. Kinsey, C. Grandy, A. Qualls, N. Brown, J. Powers, E. Hoffman, D. Croson
Nuclear Technology | Volume 199 | Number 2 | August 2017 | Pages 111-128
Technical Paper | doi.org/10.1080/00295450.2017.1336029
Articles are hosted by Taylor and Francis Online.
An assessment of advanced reactor technology options was conducted to provide a sound comparative technical context for future decisions by the U.S. Department of Energy (DOE) concerning these technologies. Strategic objectives were established that span a wide variety of important missions, and advanced reactor technology needs were identified based on recent DOE and international studies. A broad team of stakeholders from industry, academia, and government was assembled to develop a comprehensive set of goals, criteria, and metrics to evaluate advanced irradiation test and demonstration reactor concepts. Point designs of a select number of concepts were commissioned to provide a deeper technical basis for evaluation. The technology options were compared on the bases of technical readiness and the ability to meet the different strategic objectives. Using the study’s evaluation criteria and metrics, an independent group of experts from industry, universities, and national laboratories scored each of the point designs. Pathways to deployment for concepts of varying technical maturities were estimated for the different demonstration systems with regard to cost, schedule, and possible licensing approaches. This study also presents the trade-offs that exist among the different irradiation test reactor options in terms of the ability to conduct irradiations in support of advanced reactor research and development and to serve potential secondary missions.
The main findings of the study indicate the following: (1) for industrial process heat supply, a high-temperature gas-cooled reactor is the best choice because of the high outlet temperature of the reactor and its strong passive and inherent safety characteristics; (2) for resource utilization and waste management, a sodium-cooled fast reactor (SFR) is best because of the use of a fast flux to destroy actinides; (3) to realize the advantages of a promising but less-mature technology, a fluoride salt-cooled high-temperature reactor and a lead-cooled fast reactor fare about the same; (4) for fulfilling the needs of a materials test reactor, a SFR is considered best because of its ability to produce high fast flux, incorporate test loops, and provide additional large volumes for testing.