ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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.
M. J. Plaster, B. Basoglu, C. L. Bentley, M. E. Dunn, A. E. Ruggles, A. D. Wilkinson, T. Yamamoto, H. L. Dodds
Nuclear Technology | Volume 111 | Number 2 | August 1995 | Pages 219-226
Technical Paper | Nuclear Criticality Safety Special / Nuclear Criticality Safety | doi.org/10.13182/NT95-A35131
Articles are hosted by Taylor and Francis Online.
A hypothetical nuclear criticality accident in a waste supercompactor is examined. The material being compressed in the compactor is a homogeneous mixture of beryllium and 239Pu. The point-kinetics equations with simple thermal-hydraulic feedback are used to model the transient behavior of the system. A lumped-parameter energy balance is used to determine the bulk temperature of the system. A computer code has been developed to solve the model equations. The computer code calculates the fission power history, fission yield, bulk temperature of the system, and several other thermal-hydraulic parameters of interest. Calculations have been performed for the waste supercompactor for various material misloading configurations. The peak power for the various accident scenarios varies from 1.04 × 1017 to 4.85 × 1020 fissions per second (fps). The total yield varies from 8.21 × 1017 to 7.73 × 1018 fissions, and the bulk temperature of the system varies from 412 to >912 K.