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 Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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.
M. Subbotin, M. Rozenkevich, A. Gostev, A. Bukin, V. Khripunov, V. Kochin, S. Marunich, Yu. Pak, A. Perevezentsev, G. Sharova
Fusion Science and Technology | Volume 76 | Number 3 | April 2020 | Pages 297-303
Technical Paper | doi.org/10.1080/15361055.2020.1711851
Articles are hosted by Taylor and Francis Online.
The tokamak Ignitor project is one of the main topics of long-term scientific cooperation between the Russian Federation and the Italian Republic. The tokamak Ignitor has a super-strong magnetic field (13 T) and a powerful discharge current (11 MA for 10 s). Ohmic heating is the main mechanism for the ignition of the fusion reaction.
The location of the tokamak Ignitor on the Russian side has been proposed to be the complex Tokamak with Strong Field (TSP complex), which is located on the JSC “SRC RF TRINITI” (TRINITI) Joint Stock Company – State Research Center of Russian Federation Troitsk Institute for Innovation and Fusion Research site (Moscow, Troitsk, Russia). The TSP complex has unique engineering and physical and energy infrastructure, but it will be necessary to deeply modernize the infrastructure.
In the phase of the deuterium-tritium experiments on the tokamak Ignitor, providing a total tritium flow of 10 to 15 g/day will be required. Therefore, it is necessary to consider the development of a full-scale tritium complex with the entire set of solved tasks for the preparation and supply of the fuel mixture, the purification of the plasma exhaust products, and the separation of the isotopes.
