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.
Nuclear Nonproliferation Policy
The mission of the Nuclear Nonproliferation Policy Division (NNPD) is to promote the peaceful use of nuclear technology while simultaneously preventing the diversion and misuse of nuclear material and technology through appropriate safeguards and security, and promotion of nuclear nonproliferation policies. To achieve this mission, the objectives of the NNPD are to: Promote policy that discourages the proliferation of nuclear technology and material to inappropriate entities. Provide information to ANS members, the technical community at large, opinion leaders, and decision makers to improve their understanding of nuclear nonproliferation issues. Become a recognized technical resource on nuclear nonproliferation, safeguards, and security issues. Serve as the integration and coordination body for nuclear nonproliferation activities for the ANS. Work cooperatively with other ANS divisions to achieve these objective nonproliferation policies.
2021 Student Conference
April 8–10, 2021
North Carolina State University|Raleigh Marriott City Center
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
Latest Journal Issues
Nuclear Science and Engineering
Fusion Science and Technology
A day in the life of the nuclear community
The November issue of Nuclear News is focused on the individuals who make up our nuclear community.
We invited a small group of those individuals to tell us about their day-to-day work in some of the many occupations and applications of nuclear science and technology, and they responded generously. They were ready to tell us about the part they play, together with colleagues and team members, in supplying clean energy, advancing technology, protecting safety and health, and exploring fundamental science.
In these pages, we see a community that can celebrate both those workdays that record progress moving at a steady pace and the exceptional days when a goal is reached, a briefing is delivered, a contract goes through, a discovery is made, or an unforeseen challenge is overcome.
The Nuclear News staff hopes that you enjoy meeting these members of our community—or maybe get reacquainted with friends—through their words and photos.
S. A. Musa, D. S. Lee, S. I. Abdel-Khalik, M. Yoda
Fusion Science and Technology | Volume 75 | Number 8 | November 2019 | Pages 879-885
Technical Paper | dx.doi.org/10.1080/15361055.2019.1643683
Articles are hosted by Taylor and Francis Online.
The Georgia Institute of Technology group has performed studies to characterize the thermal hydraulics of a single “finger” module of the helium-cooled modular divertor with multiple jets (HEMJ) proposed for long-pulse magnetic fusion reactors in a helium (He) loop designed with maximum mass flow rate of 10 g/s. However, testing divertor modules at prototypical heat fluxes and temperatures remains an engineering challenge. A new larger helium loop with a maximum mass flow rate of 100 g/s, suitable for evaluating helium-cooled divertors with larger surface areas such as a nine-finger HEMJ module, is currently being constructed. This work presents an experimental validation of a numerical model exploring the applicability of the “reversed heat flux approach,” which cools (versus heats) the plasma-facing surface of the divertor module to evaluate the helium-side heat transfer coefficient (HTC). The approach is to be used for performance evaluation of single and multiple modules of HEMJ in existing and future large helium loops.
A cooling facility for producing a jet of water with a maximum mass flow rate of 1.4 kg/s at a maximum pressure of 0.4 MPa and temperature of 295 K (Re = 2.2 × 105) is described. Numerical and experimental results are presented for the heat flux and average helium impingement surface temperature over a range of water flow rates (0.5 to 1.4 kg/s) for heat fluxes as high as 5 MW/m2.
The numerical model suggests that the HTC of the water impingement surface is comparable to or greater than that of the helium impingement surface. For given helium and water temperatures, the heat flux values are generally limited by conduction across the outer shell. These initial studies provide guidance on extending this approach to estimating the thermal-hydraulic performance of larger divertor module designs while reducing the challenges associated with studying such designs in the normal heating configuration at their extremely high prototypical temperatures and incident heat fluxes.