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Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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2024 ANS Winter Conference and Expo
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Remembering ANS President John Kelly
John Kelly, ANS past president (2018–19 ), passed away peacefully in his sleep on October 3, 2024, in Gilbert Ariz., at the age of 70. Kelly was born on March 9, 1954, and was the eldest of Jack and Aileen Kelly’s six children.
His career, which spanned more than 40 years, began at Sandia National Laboratories in Albuquerque, N.M., where he focused on safety and severe accident analysis. His leadership led him to Washington D.C., where he served as the deputy assistant secretary for nuclear reactor technologies at the U.S. Department of Energy. Kelly played a critical role in shaping nuclear policy and guiding the world through significant events, including the Fukushima Daiichi accident in Japan. At the end of his career, he was honored to serve as the American Nuclear Society’s president. In retirement, he was actively involved with ANS in technology events and mentoring the next generation of scientists.
Kelly is survived by his wife, Suzanne; his children Julie Kelly-Smith (Byron), John A. (Sarah), and Michael (Nicole); and grandchildren Kiri and Kyson Smith and John and Maximilian Kelly. His family was his pride and joy, including his cherished dog, Covie, who brought him happiness in recent years.
In lieu of flowers, donations may be made to the American Nuclear Society or Detroit Catholic Central High School (27225 Wixom Road, Novi, MI 48374). Please designate Memorial and specify John Kelly ’72 Memorial Fund.
In honor of Kelly's commitment to ANS and to celebrate his life, his profile from the July 2018 issue of Nuclear News is published below.
J. B. Clarity, K. Banerjee, H. K. Liljenfeldt, W. J. Marshall
Nuclear Technology | Volume 199 | Number 3 | September 2017 | Pages 245-275
Technical Paper | doi.org/10.1080/00295450.2017.1361250
Articles are hosted by Taylor and Francis Online.
A novel assessment has been completed to determine the previously unquantified and uncredited criticality margin available in as-loaded commercial spent nuclear fuel (SNF) canisters. This assessment was performed as part of a broader effort to assess issues and uncertainties with storage, subsequent transportation, and final disposal of SNF canister systems. Detailed analyses crediting the burnup, initial enrichment, and postirradiation cooling time of actual SNF inventory were performed for 554 SNF canisters stored at 23 commercial reactor sites to determine realistic criticality safety margins. These detailed analyses were automated by the Used Nuclear Fuel-Storage, Transportation & Disposal Analysis Resource and Data System (UNF-ST&DARDS), a comprehensive, integrated data and analysis tool. Calculated, uncredited criticality margins (Δkeff) with respect to the safety analysis results range from 0 to almost 0.30 Δkeff for normal storage and transportation cases. Calculated eigenvalues (keff) range from 0.72 to 1.11 assuming a degraded neutron absorber disposal condition, and they range from 0.94 to 1.20 assuming a degraded basket disposal condition. Calculations with NaCl present in the moderator (which is possible for certain disposal geologies) were used to demonstrate the possibility for subcriticality for degraded cases with a keff above 0.98 with freshwater. The methods used to calculate keff for the canisters analyzed in this work are discussed in detail.
The results demonstrate that, for the majority of canisters analyzed here, significant uncredited safety margin is available that could be used to compensate for uncertainties in the SNF assembly and canister internal components. These uncertainties are associated with long-term storage and subsequent transportation and disposal. Results also suggest that the inherent margins associated with how canisters are loaded could support future changes in licensing SNF storage and transportation systems to directly or indirectly credit the margins associated with actual SNF characteristics. Ongoing research continues to gather additional data to quantify uncredited safety margins for SNF canisters loaded at other nuclear reactor sites and to explore potential methods for applying this uncredited margin.
