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
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
Technical Session
Monday, July 22, 2024|3:15–5:05PM CDT|Madison Ballroom
Session Chair:
Iole Palermo
Session Organizers:
Paul P. Wilson (University of Wisconsin-Madison)
Alternate Chair:
Ethan Peterson (Massachussets Institute of Technology)
To access paper attachments, you must be logged in and registered for the meeting.
Register NowLog In
Lithium Enrichment Needs for Different Tritium Breeding Blanket Concepts
3:15–3:40PM CDT
P.W. Humrickhouse (ORNL), M.L. Gehrig (ORNL)
Paper
Coupled Neutronics and Thermal Hydraulics Simulation of Tritium Breeding and Its Transport in the ARC-Class Fusion Blanket
3:40–4:05PM CDT
Arpan Sircar (ORNL), Jin Whan Bae (ORNL), Katarzyna Borowiec (ORNL), Vittorio Badalassi (ORNL), Cami Collins (ORNL)
Tritium Speciation and Transport in Molten Salts: Insights from the BABY Experiment
4:05–4:25PM CDT
N. Goles (MIT), R. Delaporte-Mathurin (MIT), C.S. Dunn (MIT), E. Edwards (MIT), S.E. Ferry (MIT), E. Lamere (MIT), A.T. Lanzrath (MIT), R. Leccacorvi (MIT), S. Meschini (MIT), E.E. Peterson (MIT), S. Segantin (MIT), R.F. Vieira (MIT), D.G. Whyte (MIT), K.B. Woller (MIT), W. Zhou (MIT)
Neutronics Analysis and Uncertainty Quantification of LiCl-LiF Molten Salt as a Liquid Tritium Breeding Blanket
4:25–4:45PM CDT
C.S. Dunn (MIT), E.E. Peterson (MIT), B. Ebiwonjumi (MIT), S. Segantin (MIT), W. Zhou (MIT), S. Ferry (MIT), K. Woller (MIT)
Molten Salt Activation Considerations in D-T Fusion Tokamak Design
4:45–5:05PM CDT
Austin Carter (Commonwealth Fusion Systems), Caroline Sorensen Barthel (Commonwealth Fusion Systems), Ryanne Kennedy (Commonwealth Fusion Systems)
To join the conversation, you must be logged in and registered for the meeting.