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
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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
Thursday, October 7, 2021|8:30–10:10AM EDT
Session Chair:
Andrew Holcomb (ORNL)
Session Organizers:
Benoit Forget (MIT)
William Wieselquist (ORNL)
Student Producer:
Vincent Novellino (NC State Univ.)
To access the session recording, you must be logged in and registered for the meeting.
Register NowLog In
To access session resources, you must be logged in and registered for the meeting.
Presentation Video (Visible to Attendees) — Labarile
To access paper attachments, you must be logged in and registered for the meeting.
Multigroup Material Cross-Sections Generation With SCALE 6.2.3 for Deterministic Neutron Transport Calculations: Application to a PWR Fuel Element Analysis
8:30–8:55AM EDT
Antonella Labarile (Universitat Politecnica Valencia), Arturo Vivancos (Universitat Politècnica València), Alvaro Bernal (Nuclear Safety Council), Teresa Barrachina (Universitat Politècnica València), Rafael Miró (Universitat Politècnica de València), Gumersindo Verdu (Universitat Politecnica de Valencia)
Paper
Best Estimate Schemes in Lattice Calculations for Industrial Cases, With the Help of a New Leakage Synthetic Algorithm
8:55–9:20AM EDT
B. Vezzoni (Framatome), S. Santandrea (CEA), L. Graziano (Framatome), I. Zmijarevic (CEA)
A Group-Dependent Equivalent Dancoff Factor Cell Method Applied to AIC Control Rod Calculations
9:20–9:45AM EDT
Li Mao (CEA), Igor Zmijarevic (CEA), Richard Sanchez (CEA), Nicolas Gerard Castaing (CEA)
Fuel Assembly Analyses With Resonance Calculation Using Energy Spectrum Expansion Method
9:45–10:10AM EDT
Ryoichi Kondo (Nagoya Univ.), Tomohiro Endo (Nagoya Univ.), Akio Yamamoto (Nagoya Univ.), Satoshi Takeda (Osaka University), Hiroki Koike (Mitsubishi Heavy Industries), Kazuya Yamaji (Mitsubishi Heavy Industries), Daisuke Sato (Mitsubishi Heavy Industries)
To join the conversation, you must be logged in and registered for the meeting.