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 8–12, 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
Nov 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
December 2025
Nuclear Technology
November 2025
Fusion Science and Technology
Latest News
U.K. consents to Hinkley Point B decommissioning
The U.K. government’s Office for Nuclear Regulation has granted EDF Energy formal consent to decommission the Hinkley Point B nuclear power plant in Somerset, England. The two-unit advanced gas-cooled reactor was permanently shut down in August 2022, and site owner EDF applied to ONR for decommissioning consent in August 2024.
Richard F. Mattas
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1487-1492
ITER | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29551
Articles are hosted by Taylor and Francis Online.
The performance of the ITER first wall and divertor have been analyzed using the Fusion Lifetime Prediction (FLIP) code. The code is a one-dimensional finite difference code which calculates the changes in properties, stress, strain, and temperature overtime for plate structures. The results indicate that the first wall should be able to accommodate up to ∼0.6 MW/m2 heat flux for the reference operating conditions. At much higher levels, fatigue and cracking are predicted to lead to rapid failure. The loss of ductility in irradiated austenitic stainless steel at low temperatures is a concern which may limit operating life. The results of the divertor analysis show that a bare, 2 mm thick plate of Nb-1Zr or TZM can accommodate fluxes of 15–20 MW/m2 for the ITER conditions. Duplex structures composed of 2 mm of tungsten on 2mm of Nb-1Zr or TZM are limited to 8–10 MW/m2.