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
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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.
Lance L. Snead, Roger A. Vesey†
Fusion Science and Technology | Volume 24 | Number 1 | August 1993 | Pages 83-96
Technical Paper | Divertor System | doi.org/10.13182/FST93-A30176
Articles are hosted by Taylor and Francis Online.
The primary concerns in the design of a divertor component are the high heat fluxes (15 to 30 MW/m2) and the surface erosion due to plasma/wall interactions, along with the associated issue of plasma contamination. A continuous belt, which would pass between two rollers inside the vacuum vessel, is proposed as the divertor surface to provide higher heat flux handling capability as well as reduced total erosion. Thermal analyses indicate that a belt passing from one roller through the divertor region to a cooling roller can achieve a cycle-to-cycle steady state while maintaining acceptable temperatures. The belt speed determines the amount of plasma energy absorbed per cycle and thus determines the maximum belt temperature and the requirements of the cooling roller. The belt material initially considered is a metal matrix/carbon fiber composite in which the carbon fibers are oriented out-of-plane in a 1-mm-thick metal belt. The carbon fibers protrude from the plasma-facing side of the belt, presenting the plasma ions a low-Z surface to impact. Because the belt surf ace passes through the entire divertor region, the erosion due to sputtering is uniform along the belt. Estimated gross erosion rates for a 7-m belt at expected International Thermonuclear Experimental Reactor (ITER) conditions are 5 to 10 cm/burn-yr. Electromagnetic forces and secondary magnetic fields induced by the belt motion appear manageable for a sufficiently resistive or toroidally segmented belt. In situ deposition of a sacrificial carbon layer will be required to replace eroded material. Such a belt also offers the possibility of continuous removal of the plasma-codeposited carbon and tritium layer prior to deposition of the sacrificial carbon.