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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Fusion Science and Technology
February 2024
Latest News
From South Korea to Belgium: Testing a high-density research reactor fuel
The Korea Atomic Energy Research Institute has developed a high-density uranium silicide fuel designed to replace high-enriched uranium in research reactors. Recent irradiation tests appear to be successful, KAERI reports, which means the fuel could be commercialized to continue a key global nuclear nonproliferation effort—converting research reactors to run on low-enriched uranium fuel.
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%.