ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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!
Latest Magazine Issues
Oct 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
November 2024
Nuclear Technology
Fusion Science and Technology
Latest News
The DOE picks six HALEU deconverters. What have we learned?
The Department of Energy announced contracts yesterday for six companies to perform high-assay low-enriched uranium (HALEU) deconversion and to transform enriched uranium hexafluoride (UF6) to other chemical forms, including metal or oxide, for storage before it is fabricated into fuel for advanced reactors. It amounts to a first round of contracting. “These contracts will allow selected companies to bid on work for deconversion services,” according to the DOE’s announcement, “creating strong competition and allowing DOE to select the best fit for future work.”
J. Sercombe, V. D’Ambrosi, S. Béjaoui, I. Zacharie-Aubrun
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 269-284
Research Article | doi.org/10.1080/00295450.2023.2188138
Articles are hosted by Taylor and Francis Online.
This paper presents 2D(r,) simulations of the HBC-4 power-to-melt experiment performed with the fuel performance code ALCYONE. The HBC-4 experiment is one of the two test cases selected for the simulation exercise on past fuel melting experiments of the Power to Melt and Maneuverability (P2M) project. The ramp terminal level (RTL) at peak power node (PPN) has been estimated at 66 kW·m−1 by gamma scanning and 70 kW·m−1 based on online measurements of thermal fluxes. The fuel burnup at PPN was close to 60 GWd/tU−1. The cladding failed during the short holding time at a RTL of 40 s. Fuel melting took place at the pellet center, and in particular, in front of clad cracks.
In this paper, simulations of the HBC-4 power-to-melt experiment are performed using an updated version of the 2D(r,) scheme of ALCYONE where half of the fuel pellet is described. This configuration allows for the modeling of clad failure by iodine stress corrosion cracking and of its consequences on fuel pellet deformation. The modeling of fuel melting relies on thermochemical equilibrium calculations performed with the OpenCalphad Gibbs Energy Minimizer and the Thermodynamics of Advanced Fuels International Database. The simulation without clad failure indicates that the solidus is reached during the HBC-4 experiment but not the liquidus. The simulation with clad failure leads to a small increase in the fuel temperature that is sufficient to reach the liquidus at the pellet center, in agreement with postirradiation examination (PIE). The impact of water ingress in the rod and vaporization at the pellet surface is discussed, showing that it could explain the pronounced swelling of the fuel pellet reported from the PIE.