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
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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!
Latest Magazine Issues
Apr 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
May 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Glass strategy: Hanford’s enhanced waste glass program
The mission of the Department of Energy’s Office of River Protection (ORP) is to complete the safe cleanup of waste resulting from decades of nuclear weapons development. One of the most technologically challenging responsibilities is the safe disposition of approximately 56 million gallons of radioactive waste historically stored in 177 tanks at the Hanford Site in Washington state.
ORP has a clear incentive to reduce the overall mission duration and cost. One pathway is to develop and deploy innovative technical solutions that can advance baseline flow sheets toward higher efficiency operations while reducing identified risks without compromising safety. Vitrification is the baseline process that will convert both high-level and low-level radioactive waste at Hanford into a stable glass waste form for long-term storage and disposal.
Although vitrification is a mature technology, there are key areas where technology can further reduce operational risks, advance baseline processes to maximize waste throughput, and provide the underpinning to enhance operational flexibility; all steps in reducing mission duration and cost.
S. M. An, K. S. Ha, B. T. Min, H. Y. Kim, J. H. Song
Nuclear Technology | Volume 189 | Number 2 | February 2015 | Pages 133-142
Technical Paper | Reactor Safety | doi.org/10.13182/NT14-24
Articles are hosted by Taylor and Francis Online.
The ablation kinetics of special concrete, which has been developed as one of the candidate protecting materials for the EU-APR1400 ex-vessel core catcher, was investigated experimentally. Metallic corium and stainless steel melts were generated using an induction heating technique in a cold crucible and used for the interaction tests with the special concrete. The melt delivery system was designed to prevent the melt impingement effect and chemical changes of the concrete specimen owing to preheating during the melt generation process. The metallic corium melts above the activation temperature interacted with the concrete specimens very intensively, which led to an abrupt increase of concrete ablation. However, in the interactions with the steel melts, the concrete specimens were ablated slowly even though the melt temperatures were higher than the metallic corium melts. A postanalysis of the chemical compositions and microstructures of the ingot with the ablated concrete was performed to understand the ablation phenomena. It was found that the U and Zr contained in the metallic corium melt reacted with the oxygen released by the dissociation of ferric oxides in the special concrete above the activation temperature. As a result of the exothermic reaction, both the ablation rate and the reaction layer coefficient were increased with a higher melt temperature and exhibited higher values than those in the interactions with the steel melt. Moreover, it was verified that the oxidation quotients of U and Zr are higher than those of Fe and Cr.