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
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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.
L. Romero, L. Moreno, I. Neretnieks
Nuclear Technology | Volume 112 | Number 1 | October 1995 | Pages 89-98
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT95-A15854
Articles are hosted by Taylor and Francis Online.
Radionuclides leaking from a damaged canister spread into the backfill material surrounding the canister and then migrate through different pathways into water-bearing fractures in the rock surrounding the nuclear waste repository. If the backfill and other materials surrounding the canister have a low permeability, water flow is then excluded from these materials, and the solute transport is by diffusion only. Some nuclides are delayed by sorption on the materials through which they move, and those nuclides with short half-lives may decay to insignificant concentrations before they reach the flowing water in the fractures in the rock. This complex and variable transport geometry is modeled using a compartment model. The NUCTRAN compartment model is a useful tool to calculate the nonstationary transport of single nuclides or radionuclide chains. The model, which is a very coarsely discretized integrated finite difference model, is devised to be very fast and compact by embedding analytical solutions at sensitive points such as entrances and exits from small holes and fractures. The nuclide inventory in the source may be calculated using a solubility limit approach or a congruent dissolution approach. The model is flexible and can easily be adapted to various geometries. NUCTRAN agrees well with models using a very detailed discretization. Accuracy is gained if compartments with very large capacities are subdivided into a few compartments.