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
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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
Feb 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
February 2025
Latest News
Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
Thanh Q. Hua, Basil F. Picologlou
Fusion Science and Technology | Volume 19 | Number 1 | January 1991 | Pages 102-112
Technical Paper | Blanket Engineering | doi.org/10.13182/FST91-A29320
Articles are hosted by Taylor and Francis Online.
The magnetohydrodynamic flow of a liquid metal through a manifold that feeds an array of electrically coupled rectangular ducts with thin conducting walls is investigated. This geometry is typical of an inlet/outlet manifold servicing arrays of poloidal coolant channels in tokamak self-cooled blankets. The interaction parameter and Hartmann number are assumed to be large, whereas the magnetic Reynolds number is assumed to be small. Under these assumptions, which are relevant to liquid-metal flows in self-cooled tokamak blankets, viscous and inertial effects are confined to very thin boundary layers adjacent to the walls. The analysis for obtaining three-dimensional solutions outside these layers is described, and numerical solutions are presented. Electrical coupling between the common manifold and the coolant ducts, as well as coupling among the coolant ducts themselves, necessitates simultaneous solutions for the multiple channels, and uniquely determines the partition of the total flow rate among the coolant ducts. Control of flow partition that may be required for optimal cooling of the first wall and blanket is demonstrated and discussed. The pressure drop resulting from the disturbance associated with the manifold is calculated and is shown to be minimal.