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
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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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 Science and Engineering
June 2025
Nuclear Technology
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Latest News
NRC v. Texas: Supreme Court weighs challenge to NRC authority in spent fuel storage case
The State of Texas has not one but two ongoing federal court challenges to the Nuclear Regulatory Commission that could, if successful, turn decades of NRC regulations, precedent, and case law on its head.
T. R. Moffette
Nuclear Technology | Volume 25 | Number 4 | April 1975 | Pages 630-634
Technical Paper | Reactor Siting | doi.org/10.13182/NT75-A16119
Articles are hosted by Taylor and Francis Online.
The high temperature gas-cooled reactor has inherent safety characteristics that permit this class of reactor to comply with the siting requirements of 10 CFR 100 with unique ease, particularly regarding the exclusion area boundary. As a consequence, the size of the reactor site can be selected without regard to 10 CFR 100, and the possibility of locating closer to populated areas is eased. The inherent safety characteristics are the all-ceramic reactor core with pyrocarbon fuel cladding, which can withstand very high temperatures, and the large mass of the core-graphite, which has a great thermal criteria. As a consequence, a slow “time-dependent” release of fission products to the containment would occur in the event of a hypothetical TID-type accident.