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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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!
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Latest News
State legislation: Colorado redefines nuclear as “clean energy resource”
Colorado Gov. Jared Polis signed a bill into law on Monday that adds nuclear to the state’s clean energy portfolio—making nuclear power eligible for new sources of project financing at the state, county, and city levels.
C. Fagan, M. Sharpe, W. T. Shmayda, W. U. Schröder
Fusion Science and Technology | Volume 71 | Number 3 | April 2017 | Pages 275-280
Technical Paper | doi.org/10.1080/15361055.2017.1293456
Articles are hosted by Taylor and Francis Online.
The concentration of tritium in the adsorbed water layer on stainless-steel type 316 is notably higher than that present in the metal lattice. The absorbed waters play a key role in the migration of tritium into the metal. In this work, stainless-steel (type 316) surfaces were subjected to various pretreatments designed to alter the surface in order to probe the relation between surface conditions and total tritium inventories. These pretreatments included electropolishing and soaking in nitric-acid baths. Stainless-steel samples were loaded with tritium by exposure to a deuterium–tritium gas mixture at 25°C for 24 h. Total tritium inventories were measured using temperature-programmed desorption. The thermal desorption data show a reduction of 65% in total tritium inventory by electropolishing stainless-steel surfaces as compared to unmodified samples. It is also shown that treating the surfaces with nitric acid resulted in an increase in the tritium content by ~200%.