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
Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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.
Chikara Konno, Yukio Oyama, Fujio Maekawa, Yujiro Ikeda, Kazuaki Kosako, Hiroshi Maekawa, Mohamed A. Abdou, Edgar F. Bennett, Anil Kumar, Mahmoud Z. Youssef
Fusion Science and Technology | Volume 28 | Number 2 | September 1995 | Pages 347-365
Technical Paper | Fusion Neutronics Integral Experiments — Part II / Blanket Engineering | doi.org/10.13182/FST95-A30650
Articles are hosted by Taylor and Francis Online.
Neutronics experiments on annular blanket systems that use a pseudoline source are performed. The shape of the annular blanket system is a rectangular parallelepiped (1300 × 1300 mm2 and 2040 mm long) with an inner cavity of 425.5 × 425.5 mm2 and 2040 mm long. The annular blanket consists of a 15-mm-thick first wall (Type 304 stainless steel) and 406-mm-thick breeder zone (inner lithium oxide and outer lithium carbonate). Deuterium-tritium neutron sources are set at the center of the inner cavity of the annular blanket system, and the pseudoline source is obtained by oscillating the annular blanket system back and forth in a 2-m span. Three annular blanket configurations are examined: the reference blanket, a blanket covered with 25-mm-thick graphite armor, and an armor blanket with a large opening (376 × 425.5 mm). The neutronics parameters of tritium production rate, neutron spectrum, and activation reaction rate are measured with specially developed techniques, including a multidetector data acquisition system, a spectrum weighting function method, and a ramp-controlled high-voltage system. Measured parameters are compared among three different configurations of the experimental system and also with the results of a closed geometry with a point source. A calculation with the GMVP Monte Carlo code that uses the JENDL-3 nuclear data library is performed and shows agreement within 10%. The current experiment provides unique data for a higher step of benchmark to test the ability of neutronics design calculations for a realistic tokamak reactor.