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
Oct 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
November 2025
Nuclear Technology
October 2025
Fusion Science and Technology
Latest News
Russia withdraws from 25-year-old weapons-grade plutonium agreement
Russia’s lower house of Parliament, the State Duma, approved a measure to withdraw from a 25-year-old agreement with the United States to cut back on the leftover plutonium from Cold War–era nuclear weapons.
A. Badawi, A.R. Raffray, A. Ying, M.A. Abdou
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1532-1537
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-A29559
Articles are hosted by Taylor and Francis Online.
This paper presents an analysis of the tritium release and inventory in the US-ITER solid breeder blanket, based on the MISTRAL code. Since the effect of LiOT formation and precipitation at low temperature can be quite important in Li2O, the selected solid breeder for the blanket, these processes have to be accounted for in the calculations. A simple way of estimating the LiOT precipitation as a function of temperature and moisture partial pressure was added to MISTRAL by including the calculations of T2O, H2O and HTO concentrations in the pore, in addition to T2, H2 and HT. The analysis was carried out for both steady state and transient cases. The transient cases are based on the given burn and dwell times during the Physics and Technology Phases and the corresponding temperature profile and tritium generation history in the solid breeder region. For the steady state case, a tradeoff analysis is done for the helium purge flow rate, based on an acceptable tritium inventory which imposes a lower limit on the purge flow rate and an acceptable purge pressure drop which imposes a higher limit on the purge flow rate.