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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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.
Russell D. Mosteller, Frank J. Rahn
Nuclear Technology | Volume 110 | Number 2 | May 1995 | Pages 168-180
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT95-A35116
Articles are hosted by Taylor and Francis Online.
The possibility of recriticality during the reflood phase of a severe accident in a boiling water reactor (BWR) is investigated. In addition, the fraction of control-rod material that must be retained to prevent recriticality is determined for several different geometries. Detailed calculations for a representative portion of a BWR core are performed with the Monte Carlo MCNP code to evaluate the neutronic response of the damaged core under a number of different scenarios. Retention of <10% of the 10B that is initially present in the control rods may be sufficient to prevent recriticality. The reactivity effect of the retained 10B is sensitive to the porosity and homogeneity of the eutectic formed by the control rod materials as well as to the degree to which that eutectic is dispersed inside the fuel bundles.