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
2026 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
Latest Magazine Issues
Jul 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
September 2026
Nuclear Technology
August 2026
Fusion Science and Technology
Latest News
Gov. Sherrill signs bill to begin nuclear procurement in N.J.
On July 13, New Jersey Gov. Mikie Sherrill signed the Power NJ Act, a bill that directs the state’s Board of Public Utilities (BPU), in collaboration with the state’s Economic Development Authority, to establish an “advanced nuclear energy procurement program.”
David Murdoch, Ch. Day, M. Glugla, R.oLaesser, A.Mack, R.-D. Penzhorn, A.Busigin, K.oMaynard, O. Kveton
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 1018-1022
Purification and Chemical Process | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22738
Articles are hosted by Taylor and Francis Online.
The European Home Team has designed several of the key systems in the ITER Fuel Cycle and carried out R&D to validate critical features of the processing concepts adopted and components proposed. System designs for Tokamak Exhaust Processing (TEP), Storage and Delivery (SDS), Isotope Separation (ISS) and Tritium plant Analytical Systems (ANS) have been generated, with emphasis placed on measures to minimise tritium inventory. Design integration studies and dynamic simulations of tritium inventory behaviour have been performed. Recent TEP R&D has focussed on upgrading of the test loop for integrated testing of gas streams representative of all modes of operation, including tritium recovery from Plasma Facing Components (PFC s). Tests to characterise tritium inventories in PFC s and develop processes for quantitative recovery of this tritium are under way. A near ITER scale Torus Exhaust cryopump has been tested and the pumping speed design calculations validated. Tests to ensure that ISS product quality can be maintained during fluctuations in feed conditions have been successfully carried out. Construction of an ITER-scale tritium storage bed is in progress.