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
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
Michael T. Itamura, Nicholas D. Francis, Jr., Stephen W. Webb, Darryl L. James
Nuclear Technology | Volume 148 | Number 2 | November 2004 | Pages 115-124
Technical Paper | High-Level Radioactive Waste Disposal | doi.org/10.13182/NT04-A3552
Articles are hosted by Taylor and Francis Online.
Yucca Mountain has been designated as the nation's high-level radioactive waste repository, and the U.S. Department of Energy has been approved to apply to the U.S. Nuclear Regulatory Commission for a license to construct a repository. The temperature and humidity inside the emplacement drift will affect the degradation rate of the waste packages and waste forms as well as the quantity of water available to transport dissolved radionuclides out of the waste canister. Thermal radiation and turbulent natural convection are the main modes of heat transfer inside the drift. This paper presents the result of three-dimensional computational fluid dynamics simulations of a segment of emplacement drift. The model contained the three main types of waste packages and was run at the time that the peak waste package temperatures are expected. Results show that thermal radiation is the dominant mode of heat transfer inside the drift. Natural convection affects the variation in surface temperature on the hot waste packages and can account for a large fraction of the heat transfer for the colder waste packages. The paper also presents the sensitivity of model results to uncertainties in several input parameters. The sensitivity study shows that the uncertainty in peak waste package temperatures due to in-drift parameters is <3°C.