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.
Technical Session|Sponsored by THD
Monday, June 8, 2020|1:00–3:10PM EDT
Session Chair:
Marilyn Delgado
Alternate Chair:
Guillaume P. Mignot
Session Organizer:
Jun Wang
Track Organizer:
Igor Bolotnov (NCSU)
Staff Producer:
Janice Lindegard (American Nuclear Society)
WELCOME TO THE FIRST ANS VIRTUAL MEETING! This session is sponsored by the Thermal Hydraulics Division. We have four speakers within this session. The summaries are available for download. Each session will be recorded in case you miss it!
To access the session recording, you must be logged in and registered for the meeting.
Register NowLog In
To access paper attachments, you must be logged in and registered for the meeting.
High Fidelity Characterization of the Flow in a 5x5 Rod Bundle with a Customized Spacer Grid
Yassin Hassan (Texas A&M Univ.), Thien Nguyen (Texas A&M Univ.), Gabriel C. Q. Tomaz (Texas A&M Univ.), Camila F. Matozinhos (Texas A&M Univ.)
Paper
Experimental Quantification of Form Drag on Rising Bubbles Using PIV
Qiao Wu (Oregon State Univ.), Wade Marcum (Oregon State Univ.), Isaiah Wieland (Oregon State Univ.), Alexander Duenas (Oregon State Univ.)
Design of a Pebble Bed Heat Transfer Separate Effects Test
Nicolas Zweibaum (Kairos Power, LLC), Brian Woods (Oregon State Univ.), Connor Dionne (Oregon State Univ.), Shikha Kumar (Oregon State Univ.), Joshua Halsted (Oregon State Univ.), Izabela Gutowska (Oregon State Univ.), Jacob Uselman (Oregon State Univ.)
Investigation of the influence of the bundle geometry distortion on the critical heat flux
Daniya Kireeva (NRC Kurchatov Institute), Dmitry Oleksyuk (NRC Kurchatov Institute)
There are 2 comments in this discussion.
To join the conversation, you must be logged in and registered for the meeting.
