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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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Nuclear Technology
Fusion Science and Technology
February 2024
Latest News
Can hydrogen be the transportation fuel in an otherwise nuclear economy?
Let’s face it: The global economy should be powered primarily by nuclear power. And it probably will by the end of this century, with a still-significant assist from renewables and hydro. Once nuclear systems are dominant, the costs come down to where gas is now; and when carbon emissions are reduced to a small portion of their present state, it will become obvious that most other sources are only good in niche settings. I mean, why use small modular reactors to load-follow when they can just produce that power instead of buffering it?
Sunghwan Yun, Nam Zin Cho, Mu-Young Ahn, Seungyon Cho
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 232-238
Tritium, Safety, and Environment | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8908
Articles are hosted by Taylor and Francis Online.
The Korean HCSB (Helium Cooled Solid Breeder) TBM (Test Blanket Module), whose breeding zone is composed of lithium ceramic, beryllium and graphite in pebble form, was designed based on LOCAL assumption. In this research, we establish a simple preliminary GLOBAL neutronics model for the Korean HCSB TBM and perform neutronics analyses including depletion (transmutation) calculation during 500EFPDs (Effective Full Power Days) using the modified MONTEBURNS code. The neutronics characteristics for D-D plasma phase are investigated in the preliminary GLOBAL neutronics model, and the results are compared with those of D-T plasma phase. Moreover, we also establish the A-lite based GLOBAL neutronics model for more reliable neutronics calculation, and the results are compared with each other.