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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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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
Standards Program
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
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.
Sergey I. Belousov, Krassimira D. Ilieva, Stoyan Y. Antonov
Nuclear Technology | Volume 111 | Number 2 | August 1995 | Pages 270-274
Technical Paper | Nuclear Criticality Safety Special / Material | doi.org/10.13182/NT95-A35136
Articles are hosted by Taylor and Francis Online.
The neutron flux values at the sites important for the pressure vessels of the VVER-1000 and VVER-440 reactors have been calculated by the three-dimensional TORT code and the synthesis method approximation. The synthesis method is widely used now for neutron fluence routine calculations in metal embrittlement surveillance. The three-dimensional neutron flux evaluation by the synthesis method is based on the two-dimensional and one-dimensional solutions of the transport equation. The comparison of the results obtained by both methods confirms the good consistency within 3% for integral neutron flux with energy >0.5 MeV, used for metal damage estimation, according to Russian reactor standards. Further investigations on the calculation validity will be based on comparisons with measurements of the threshold detector activities, monitored in the air shell behind the reactor pressure vessels of the Kozloduy nuclear power plant.