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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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!
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Nuclear Technology
Fusion Science and Technology
July 2025
Latest News
DOE issues new NEPA rule and procedures—and accelerates DOME reactor testing
Meeting a deadline set in President Trump’s May 23 executive order “Reforming Nuclear Reactor Testing at the Department of Energy,” the DOE on June 30 updated information on its National Environmental Policy Act (NEPA) rulemaking and implementation procedures and published on its website an interim final rule that rescinds existing regulations alongside new implementing procedures.
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.