ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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.
Gary R. Smolen, Raymond C. Lloyd, Hideyuki Funabashi
Nuclear Technology | Volume 107 | Number 3 | September 1994 | Pages 304-325
Technical Paper | Nuclear Criticality Safety | doi.org/10.13182/NT94-A35010
Articles are hosted by Taylor and Francis Online.
A series of critical experiments was performed with mixed plutonium-uranium nitrate solutions in two cylinders and in a variable thickness slab tank. The solution concentrations ranged from 12 to 174 g Pu/ℓ with Pu/Pu+U ratios of 0.5, 0.4, and 0.2. The criticality data were used to validate two versions of the SCALE computer code system (SCALE-4 and SCALE-2). Calculations were performed with the 27-energy-group cross-section library, derived from the Evaluated Nuclear Data File B-Version IV. The average calculated keff for all geometries (39 experiments) is 1.006 (σ = 0.006), calculated with SCALE-4, and 1.004 (σ = 0.007), calculated with SCALE-2. Overall, the range of calculated keff varied from 0.989 to 1.019. These experiments covered a wide range of parameters, with variations in physical, chemical, and neutronic parameters.
