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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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Jul 2024
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Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Vogtle-3 shuts down for valve issue
One of the new Vogtle units in Georgia was shut down unexpectedly on Monday last week for a valve issue that has since been investigated and repaired. According to multiple local news outlets, Georgia Power reported on July 17 that Unit 3 was back in service.
Southern Company spokesperson Jacob Hawkins confirmed that Vogtle-3 went off line at 9:25 p.m. local time on July 8 “due to lowering water levels in the steam generators caused by a valve issue on one of the three main feedwater pumps.”
Milos Atz, Xudong Liu, Massimiliano Fratoni, Joonhong Ahn (Univ of California, Berkeley), Fumio Hirano (JAEA)
Proceedings | 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017) | Charlotte, NC, April 9-13, 2017 | Pages 608-614
After nuclear waste is buried in a repository, hydrogeological processes can dissolve, transport, separate, and rearrange radionuclides inside or outside the repository. If fissile material becomes separated from neutron absorbers and precipitates in a far-field geologic formation, a critical mass may be formed. Far-field criticality could greatly increase the dose to the biosphere by releasing highly mobile and radioactive fission products outside all engineered barriers.
The scope of this study is to assess the impact of the spent fuel composition and host rock type on the risk of criticality in the far field. In particular, this study performs neutronics analysis in order to determine the minimum theoretical mass of fissile material needed to achieve criticality in a water-saturated far-field deposition under conservative conditions. Light water reactor spent fuel compositions are determined using ORIGEN-ARP as a function of initial enrichment and burnup for various fuel and reactor types. Different compositions of potential host rocks are considered. For each combination of spent fuel type and host rock, the deposition minimum critical mass is obtained at 200,050 years after fuel discharge by iterative MCNP calculation in the space of initial enrichment and discharge burnup. The results are compared for different types of spent fuels to demonstrate the effects of reactor, fuel, and fuel assembly types on the minimum critical mass. Fissile material from MOX and PWR spent fuels is shown to have a smaller minimum critical mass than that of UO2 or BWR spent fuels due to increased reactivity whereas the assembly type is insignificant. For a fixed fissile content in the deposition, the critical mass increases linearly with spent fuel burnup. For representative compositions of fissile material, perturbation calculations are carried out on the composition of each host rock to identify minerals with a large impact on neutronics. Overall, this work yields insights into how the fuel cycle can be controlled to mitigate or eliminate the risk of far-field criticality. In addition, the results provide a scientific basis for future criticality safety assessment studies and the engineeringinformed decisions that will be required when repository sites are selected.