ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Securing the advanced reactor fleet
Physical protection accounts for a significant portion of a nuclear power plant’s operational costs. As the U.S. moves toward smaller and safer advanced reactors, similar protection strategies could prove cost prohibitive. For tomorrow’s small modular reactors and microreactors, security costs must remain appropriate to the size of the reactor for economical operation.
Hangbok Choi, Chang Je Park
Nuclear Technology | Volume 153 | Number 2 | February 2006 | Pages 132-145
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3695
Articles are hosted by Taylor and Francis Online.
Dry process fuel technology has high proliferation resistance, which is one of the important goals of the Generation-IV nuclear energy system developments. It is expected that dry process fuel technology can be applied not only to existing but also to future nuclear systems. In this study, the homogeneous ThO2-UO2 fuel cycle and the heterogeneous ThO2-DUPIC fuel cycle options of a Canada deuterium uranium (CANDU) reactor were assessed, which included a neutronic feasibility analysis of recycling spent fuels. Parametric calculations were also performed for reactivity coefficients and isotopic content changes for various initial fuel conditions. The results of the physics calculations have shown that it is feasible to recycle the thorium fuel through the dry process option in the CANDU reactor, which in turn significantly improves natural uranium savings and diminishes spent fuel. However, further investigation of the dry process option, which is technically and economically feasible for thorium-abundant dioxide fuel, is required.