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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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Jun 2025
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Nuclear Science and Engineering
August 2025
Nuclear Technology
July 2025
Fusion Science and Technology
Latest News
Hanford proposes “decoupled” approach to remediating former chem lab
Working with the Environmental Protection Agency, the Department of Energy has revised its planned approach to remediating contaminated soil underneath the Chemical Materials Engineering Laboratory (commonly known as the 324 Building) at the Hanford Site in Washington state. The soil, which has been designated the 300-296 waste site, became contaminated as the result of a spill of highly radioactive material in the mid-1980s.
Jeong-Hyeon Eom, Gi-Young Tak, In-Sik Ra, Ji-Won Choi, Hae-Yong Jeong
Nuclear Science and Engineering | Volume 199 | Number 1 | April 2025 | Pages S923-S940
Research Article | doi.org/10.1080/00295639.2025.2456373
Articles are hosted by Taylor and Francis Online.
The occurrence of a steam explosion resulting from fuel coolant interaction poses a significant threat to the integrity of nuclear power plants when extremely high-temperature molten corium is released into the preflooded reactor cavity. The present study establishes and verifies a computational fluid dynamics (CFD) model by simulating the TROI steam explosion experiment.
The suggested model uses the Lagrangian method to simulate particles and adopts a secondary breakup model by which the particles are fragmented based on the critical Weber number. The increased number of fine particles, surface area growth, and the propagation of the explosion pressure wave following the triggering of the steam explosion are effectively simulated with the established model. The formation of steam flow and the subsequent breakup of particles are basically governed by the heat transfer between the corium particles and the cooling fluids. The mass distribution of particle sizes after breakup is obtained by modifying the main terms of the error function, which determines the diameter of child particles to be comparable with experimentally measured distributions.
With this modeling, the maximum pressure obtained by the simulation approaches the measured peak pressure. This suggests that the established CFD model is successful in describing the overall thermal-hydraulic phenomena during a steam explosion. In the future, the steam explosion CFD model will be further enhanced to obtain a more sophisticated model to minimize the uncertainty in steam explosion predictions.