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The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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ANS Student Conference 2025
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Albuquerque, NM|The University of New Mexico
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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.
J.M. Miller, R.A. Verrall, D.S. MacDonald, S.R. Bokwa
Fusion Science and Technology | Volume 14 | Number 2 | September 1988 | Pages 649-656
Tritium Properties and Interactions with Material | Proceedings of the Third Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Toronto, Ontario, Canada, May 1-6, 1988) | doi.org/10.13182/FST88-A25208
Articles are hosted by Taylor and Francis Online.
Results from the CRITIC-I, vented capsule irradiation of Li2O are presented. A total lithium burnup of 0.74% has been achieved and 1500 curiesb of tritium have been collected over the first 15 months of irradiation. The temperature has been varied between 400 and 850°C, and the sweep gas composition changed progressively from pure He to He-1% H2. The amount of tritium recovered in the reduced form (HT) has increased from an initial value of approximately 50% with pure He sweep gas to a current value of 99% with He-1% H2. The increasing H2 concentration in the sweep gas has also reduced the time constants for tritium release (tritium residence time in the Li2O). Although the results indicate tritium release is controlled by surface desorption, simple first-order desorption theories do not explain all the observations. Most noticeably, for temperature increase tests, tritium release peak maxima can be delayed as long as 6 h and inventory changes depend not only on the initial temperature but also on the time at the initial temperature. An explanation is given based on the buildup of free oxygen in the ceramic from lithium burnup which leads to tritium trapping, perhaps as LiOH(T). Dissociation of LiOH(T) then occurs following an increase in the ceramic temperature, in addition to the simple first-order desorption process of isotopic exchange with H2 in the sweep gas.
