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.
Explore membership for yourself or for your organization.
Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
Jul 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
August 2025
Nuclear Technology
Fusion Science and Technology
July 2025
Latest News
DOE on track to deliver high-burnup SNF to Idaho by 2027
The Department of Energy said it anticipated delivering a research cask of high-burnup spent nuclear fuel from Dominion Energy’s North Anna nuclear power plant in Virginia to Idaho National Laboratory by fall 2027. The planned shipment is part of the High Burnup Dry Storage Research Project being conducted by the DOE with the Electric Power Research Institute.
As preparations continue, the DOE said it is working closely with federal agencies as well as tribal and state governments along potential transportation routes to ensure safety, transparency, and readiness every step of the way.
Watch the DOE’s latest video outlining the project here.
Neil Mitchell, Denis Bessette, Hirobumi Fujieda, Yuri Gribov, Cees Jong, Fabrice Simon
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 676-684
ITER | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST09-A8987
Articles are hosted by Taylor and Francis Online.
The ITER magnet system, particularly the Poloidal Field Coils (PFC) and Central Solenoid Coils (CSC), was originally designed to drive, confine and stabilise a set of plasmas about a baseline of a reference 15MA 400s inductive burn, with capability for inductive short burn at currents up to 17MA and 10MA non-inductive plasmas depending on the plasma parameters that can be achieved.Recent assessments of experimental data and improved plasma modelling have identified some constraints in the 2001 design that may limit the range of plasmas that can be generated in ITER. The constraints are a mixture of coil superconducting performance, structural and electrical limits, and concern both the accuracy of the formation of the plasma configuration (including the position of the separatrix lines in the divertor) and the stabilisation of the plasma position.