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
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
Latest News
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Churl Yoon, Joo Hwan Park
Nuclear Technology | Volume 160 | Number 3 | December 2007 | Pages 314-324
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT07-A3902
Articles are hosted by Taylor and Francis Online.
The fluid flows going through the Canada Deuterium Uranium (CANDU) moderator inlet diffuser assembly consist of a pipe flow, a curved pipe flow, and an impinging jet. For predicting the velocity profile at the diffuser outlet faces, a computational fluid dynamics (CFD) analysis has been performed to simulate the internal flow in the diffuser assembly. For the validation of a CFD code, some experimental data were chosen for each flow, and various turbulence models were examined. The shear stress transport turbulence model was proven to be the most appropriate for a prediction of the impinging jets and to give better predictions for a curved pipe flow compared to the standard k-[curly epsilon] turbulence model. As a result of the investigation, detailed velocity profiles and turbulent parameters at the real diffuser outlets were obtained, which can be applied as an inlet boundary condition for the CANDU moderator analysis.