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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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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Oklo completes end-to-end demonstration of advanced fuel recycling
Oklo Inc. has announced that it has completed the first end-to-end demonstration of its advanced fuel recycling process as part of an ongoing $5 million project in collaboration with Argonne and Idaho National Laboratories. Oklo’s goal: scaling up its fuel recycling capabilities to deploy a commercial-scale recycling facility that would increase advanced reactor fuel supplies and enhance fuel cost effectiveness for its planned sodium fast reactors.
M. E. Dunn, B. Basoglu, C. L. Bentley, C. Haught, M. J. Plaster, A. D. Wilkinson, T. Yamamoto, H. L. Dodds
Nuclear Technology | Volume 111 | Number 2 | August 1995 | Pages 183-196
Technical Paper | Nuclear Criticality Safety Special / Fission Reactor | doi.org/10.13182/NT95-A35129
Articles are hosted by Taylor and Francis Online.
The multigroup Monte Carlo code KENO V.a and the 238- and 44-energy-group ENDF/B-V cross-section libraries were validated for 233U systems. Fifty-one critical experiments involving 233UO2(NO3)2, 233UO2F2, or 233U metal were selected for the validation. The H/233U ratios for the experiments range from 0 to 1986. Each experiment was modeled with KENO V.a, and the effective multiplication factor keff was calculated for each system using the 44- and 238-group ENDF/B-V, the 27- and 218-group ENDF/B-IV, and the 16-group Hansen-Roach cross-section libraries. The mean calculated keff for all experiments using the 44- and 238-group libraries is 1.0090 ± 0.0021 and 1.0064 ± 0.0020, respectively. For comparison, the mean calculated keff using the 27-, 218-, and 16-group libraries is 1.0142 ± 0.0038, 1.0125 ± 0.0038, and 0.9991 ± 0.0019, respectively. In general, an improvement exists in the agreement between the calculated keff’s and the experimental results (i.e., keff= 1.0) obtained with the newer ENDF/B-V libraries relative to ENDF/B-IV.
