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
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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
Sep 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
Fusion Science and Technology
October 2025
Latest News
IAEA report confirms safety of discharged Fukushima water
An International Atomic Energy Agency task force has confirmed that the discharge of treated water from Japan’s Fukushima Daiichi nuclear power plant is proceeding in line with international safety standards. The task force’s findings were published in the agency’s fourth report since Tokyo Electric Power Company began discharging Fukushima’s treated and diluted water in August 2023.
More information can be found on the IAEA’s Fukushima Daiichi ALPS Treated Water Discharge web page.
Michael Drevlak
Fusion Science and Technology | Volume 33 | Number 2 | March 1998 | Pages 106-117
Technical Paper | doi.org/10.13182/FST98-A21
Articles are hosted by Taylor and Francis Online.
A method for finding a set of modular, poloidally closed stellarator coils confining a plasma in a given equilibrium configuration is described. The proposed technique performs a direct nonlinear optimization of the coil shapes with respect both to the desired structure of the magnetic field and to geometric constraints required by the fabrication process of the coils. This is in contrast to the method employed successfully for the design of the coil system of experiment W7-X, which divides the minimization of the field error and the adjustment of the geometric coil properties into consecutive steps. The viability of the new method is exemplified by two alternative coil designs for the plasma configuration of W7-X, offering more space inside the coils for installation of the divertor system or a blanket. The results are compared with the original coil configuration designed for W7-X.