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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 Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
Bipartisan nuclear waste bill introduced in U.S. House
U.S. representatives Mike Levin (D., Calif.) and August Pfluger (R., Texas) have introduced the bipartisan Nuclear Waste Administration Act of 2024, which would establish an independent agency to manage the country’s nuclear waste.
In addition to establishing a new, single-purpose administration to manage the back end of the nuclear fuel cycle, the bill would direct a consent-based siting process for nuclear waste facilities and ensure reliable funding for managing nuclear waste by providing access to the Nuclear Waste Fund. According to Pfluger and Levin, the bill’s provisions are in line with recommendations from the Blue Ribbon Commission on America’s Nuclear Future.
Kazuichiro Hashimoto, Kunihisa Soda, Hideo Sekiya
Nuclear Technology | Volume 87 | Number 4 | December 1989 | Pages 1058-1066
Late Paper | TMI-2: Decontamination and Waste Management / Nuclear Safety | doi.org/10.13182/NT89-A27697
Articles are hosted by Taylor and Francis Online.
A thermal-hydraulic analysis of the initial 174 min of the Three Mile Island Unit 2 (TMI-2) accident was performed using the THALES (Thermal-Hydraulic Analysis of Loss-of-Coolant, Emergency Core Cooling and Severe Core Damage)-PM1/TMI code. The purpose of the analysis was to verify whether the THALESPMl/TMI code is capable of describing an accident progression in an actual plant. The initial and boundary conditions were based on the TMI-2 Standard Problem data base that was used by the Organization for Economic Cooperation and Development/Nuclear Energy Agency Committee on the Safety of Nuclear Installations in performing the TMI-2 Analysis Exercise. The analytical results generally agree with the actual behavior, indicating that the physical models employed in the code are reasonable. Better results were obtained using this analysis concerning the core degradation behavior in the early phase of the transient in which the debris node was assumed to remain at the original location. However, the physical models for the fuel relocation and debris formation need further improvement to be consistent with accident progression in the later phases of the transient.