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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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
DOE issues final RFQ for WIPP clean energy initiative
The Department of Energy’s Office of Environmental Management has issued a request for qualifications for interested parties and prospective offerors looking to enter into a realty agreement for carbon-pollution-free electricity (CFE) projects at the department’s Waste Isolation Pilot Plant site in southeastern New Mexico.
Kyung Mo Kim, Yeong Shin Jeong, In Guk Kim, In Cheol Bang
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 598-613
Technical Paper | doi.org/10.13182/NT16-32
Articles are hosted by Taylor and Francis Online.
The importance of passive safety for commercial nuclear power plants has been emphasized after the nuclear accidents that occurred at Three Mile Island and Fukushima. A combination of unexpected human errors, severe natural disasters, and defects of system designs led to the accidents, thereby highlighting the vulnerability of established safety systems of commercial nuclear power plants. Various passive safety systems are under development to mitigate design-basis accidents. However, several uncertainties and problems have been pointed out. As a solution to the problems, this paper proposes various designs for a passive in-core cooling system (PINCs) based on hybrid heat pipes. The feasibility and coolability of the PINCs as a passive safety system for commercial pressurized water reactors was investigated using experimental works and numerical analyses. The PINCs showed sufficient coolability to mitigate station blackout conditions by delaying core uncovery. Additionally, several PINCs concepts for advanced nuclear power plants such as a small modular reactor and Generation IV reactors are suggested.