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Argonne updates: Fuel research and materials lab
Over the past two weeks, Argonne National Laboratory has announced numerous significant advancements being made by its staff to push forward nuclear fuels and materials research. Those announcements include the opening of the new Activated Materials Lab, the development of a new measurement technique, and the application of new artificial intelligence tools.
R. C. Lloyd, E. D. Clayton, J. H. Chalmers
Nuclear Technology | Volume 4 | Number 3 | March 1968 | Pages 136-141
Technical Paper and Note | doi.org/10.13182/NT68-A26376
Articles are hosted by Taylor and Francis Online.
The results of neutron multiplication measurements performed with arrays of 233U solution apply to criticality safety considerations in handling solutions at a concentration of ≈ 330 g 233U/liter and are useful in checking computational methods. The measurements were made with ≤ 17.3 kg 233U in both reflected and unreflected arrays. Critical numbers of bottles were determined as a function of spacing, and the effect of adding moderating material between the bottles comprising an array was also examined. Monte Carlo calculations were found to reproduce the experimental data reasonably well, with keff being computed to within about 0.03 of unity for those cases compared.