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Supporting ANS now, for the future
Hash Hashemianpresident@ans.org
From kindergarten classrooms to national security facilities, each event I attended during the opening weeks of the new year underscored one truth: The future of nuclear energy depends on the people we inspire, educate, and empower today.
I had a busy start to 2026, first speaking at the Nashville Energy and Mining Summit alongside Tennessee Electric Cooperative Association senior vice president Justin Maierhofer to explore the necessary synergies among policy, academic coursework, research, and industry expertise in accelerating American nuclear innovation. Drawing on experiences in high-level government relations and public affairs and decades of work in nuclear instrumentation advancements, we discussed Tennessee’s nuclear renaissance, workforce development, and policy frameworks that support emerging energy demands.
A. I. Miller, D. A. Spagnolo, J. R. DeVore
Nuclear Technology | Volume 112 | Number 2 | November 1995 | Pages 204-213
Technical Paper | Radioisotopes and Isotope | doi.org/10.13182/NT95-A35174
Articles are hosted by Taylor and Francis Online.
Tritium removal and heavy water upgrading are essential components of the heavy water-moderated reactor that is the heart of the Advanced Neutron Source (ANS) to be built at Oak Ridge National Laboratory. The technologies for these two processes, which are closely related, are reviewed in the context of the ANS requirements. The evolution of the design of the Heavy Water Upgrading and Detritiation Facility (HWUDF) for ANS is outlined, and the final conceptual design is presented. The conceptual design of HWUDF has two main component systems: (a) a front-end combined electrolysis and catalytic exchange (CECE) system and (b) a back-end cryogenic distillation (CD) system. The CECE process consists of a countercurrent exchange column for hydrogen-water exchange over a wetproofed catalyst and electrolysis to convert water into hydrogen. It accepts all the tritiated heavy water streams of the reactor and performs an almost total separation into a protium (light hydrogen) stream containing tritium and deuterium at only natural abundance and a deuterium stream containing all the tritium and almost no protium. The tritium-containing deuterium stream is then processed by a CD unit, which removes over 90% of the tritium and concentrates it to >99% tritium for indefinite storage as a metal tritide. Deuterium gas with a small residue of tritium is recombined with oxygen from the electrolytic cells and returned as heavy water to the reactor.