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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Jun 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
August 2024
Nuclear Technology
July 2024
Fusion Science and Technology
Latest News
NRC engineers share their expertise at the University of Puerto Rico
Robert Roche-Rivera and Marcos Rolón-Acevedo are licensed professional engineers who work at the U.S. Nuclear Regulatory Commission. They are also alumni of the University of Puerto Rico–Mayagüez (UPRM) and have been sharing their knowledge and experience with students at their alma mater since last year, serving as adjunct professors in the university’s Department of Mechanical Engineering. During the 2023–2024 school year, they each taught two courses: Fundamentals of Nuclear Science and Engineering, and Nuclear Power Plant Engineering.
M. Rashid, S. Rahman, R. Kulenovic, M. Bürger, E. Laurien
Nuclear Technology | Volume 181 | Number 1 | January 2013 | Pages 208-215
Technical Paper | Special Issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14) / Thermal Hydraulics | doi.org/10.13182/NT13-A15768
Articles are hosted by Taylor and Francis Online.
In the case of a severe accident, continuous unavailability of cooling water to the core will result in overheating and subsequent meltdown of the fuel elements that would eventually result in the loss of fuel integrity. Under such conditions a porous structure, which is made of heat-generating particles of different sizes and shapes, may be formed. The presence of decay heat in such a debris bed poses a critical threat to the reactor pressure vessel (RPV). To avoid any damage to the RPV, the removal of decay heat from the debris bed is of great importance. The debris bed needs to be quenched by water either flooding from the top or flooding from the bottom until continuous cooling is established. To investigate the quenching behavior of the debris bed by means of experiments, the nonnuclear test facility "DEBRIS" has been established at Institut für Kernenergetik und Energiesysteme (IKE). Experimental investigations of quenching behavior for a preheated debris bed, at various initial bed temperatures, are carried out at IKE. In the new quenching tests, the cooling-down behavior of a superheated polydispersed particle bed from stainless steel spheres at different thermohydraulic conditions has been investigated. Numerical investigation with IKE's MEWA-2D code has also been carried out for the quenching experiments in order to promote better understanding of the experimental results as well as to verify the code's applicability to the quenching process.