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
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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.
C. Konno, Y. Oyama, Y. Ikeda, K. Kosako, H. Maekawa, T. Nakamura, A. Kumar, M.Z. Youssef, M.A. Abdou, E.F. Bennett
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1885-1890
Neutronic | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29618
Articles are hosted by Taylor and Francis Online.
A pseudo line DT neutron source has been realized by moving an experimental assembly with respect to a point DT source in the Phase-III experiment of JAERI/USDOE collaborative program on fusion blanket neutronics. In order to examine characteristics of the pseudo-line source made by two types of operational modes, source term experiments were carried out. Neutron flux distribution above 10 MeV was measured by NE213 scintillator with stepwise source mode. The reaction rate distributions were also measured by activation foil technique with continuous source mode. The measured distributions were almost flat over central 1 m region of the simulated line source and agreed relatively with a simple calculation assuming the ideal line source. From these experimental results it was concluded that both modes worked successfully to obtain the pseudo-line source and could simulate well neutron flux distribution emitted from a finite length line source with small influence of reaction kinematics and target structure.