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Division Spotlight
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.
Meeting Spotlight
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.
Jack K. Boshoven
Nuclear Technology | Volume 110 | Number 1 | April 1995 | Pages 33-39
Technical Paper | Burnup Credit / Nuclear Criticality Safety | doi.org/10.13182/NT95-A35094
Articles are hosted by Taylor and Francis Online.
General Atomics (GA) is developing two legal weight truck casks for shipping spent fuel from both pressurized water reactors (PWRs) and boiling water reactors (BWRs). The GA-4 (4 PWR) and GA-9 (9 BWR) casks are high-capacity legal weight truck casks designed to transport light water reactor spent-fuel assemblies. The GA-9 cask can meet the criticality safety requirements using the “fresh fuel” assumption. To maintain a capacity of four PWR spent-fuel assemblies, the GA-4 cask uses burnup credit as part of the criticality control for initial enrichments >2.9 wt% 235U. Using the U.S. Department of Energy Burnup Credit Program as a basis, GA has performed burnup credit analysis for the GA-4 cask. The approach to calculating the minimum burnup requirement takes into account all of the key parameters affecting keff. It is based on technically sound principles and conservatively increases the burnup requirement for a given enrichment to account for all uncertainties and biases associated with the calculations.