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
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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.
Kyoung M. Kang, Michael L. Corradini
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 511-523
Technical Paper | doi.org/10.13182/NT15-157
Articles are hosted by Taylor and Francis Online.
This work proposes a model to explain concrete anisotropic ablation by corium during a molten core–concrete interaction (MCCI). As a result of recent MCCI prototypic material experiments, core-concrete interaction (CCI) tests, and VULCANO tests, one observes that concrete ablation behavior consistently depends on the concrete materials used in the experiments. Specifically, tests with limestone-common-sand (LCS) concrete yielded isotropic concrete ablation, i.e., equal axial and radial concrete erosion. This is in comparison to anisotropic ablation in tests with siliceous (SIL) concrete, where radial ablation was much larger than axial ablation. This was an unexpected result because prior results of many MCCI simulant experiments indicated that nearly isotropic ablation was expected in prototypic material experiments regardless of concrete type. A new phenomenological model is proposed in this work based on a hypothesis that unifies the result of both previous simulant and prototypic material experiments, i.e., heat transfer area enhancement and delayed gas release caused by the presence of unmelted solid aggregate material that enters the molten pool. This model offers a logical and phenomenological explanation concerning anisotropic ablation as well as the capability to simulate anisotropic ablation. This model is implemented into the CORQUENCH code as part of this work. Comparisons of these simulation results obtained with this new model to the CCI experiments for cases with SIL concrete and anisotropic ablation show better agreement with the test data than the existing model.