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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.
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ANS Student Conference 2025
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Albuquerque, NM|The University of New Mexico
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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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Latest News
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
V.L. Arbuzov, V. B. Vykhodets, G. A. Raspopova
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1127-1131
Tritium Properties and Interaction with Material | Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30558
Articles are hosted by Taylor and Francis Online.
The interaction of radiation-induced defects with deuterium atoms at room tenperature was studied for commercial vanadium, V-H and V-D alloys. During a 700 keV D+ bombardment the accumulation of D in the irradiated area was measured by means of NRA using the reaction D(d,p)T. It was shown that in the irradiated area of the V-D alloys (0.01–0.1 at .% D) the D concentration depends on both the fluence and the alloy composition. As the fluence is increased, the accumulated amount saturates. The saturation level depends on the D concentration and is 3 to 6 times as high as the D concentration in the bulk. The D segregation is due to the formation of immobile or low-mobile “D atom — radiation defect” conplexes. At the same time free D atoms are almost immediately redistributed in the bulk of the sample. A complex deuterium-protium segregation in V-D and V-H alloys under D+ bombardment was studied too. The accumulation of implanted deuterium in the irradiation-damaged area was examined for alloys with a high (0.6–2.65 at .% H) content of 1H hydrogen isotope. It is shown that the implant accumulation level is indepedent of the bombardment dose but is determined by the content of “free” protium in the alloys: the higher the protium concentration, the lower the accumulation level.
