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2024 ANS Winter Conference and Expo
November 17–21, 2024
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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.
Hyung Jin Shim, Sung Hoon Choi, Chang Hyo Kim
Nuclear Science and Engineering | Volume 176 | Number 1 | January 2014 | Pages 58-68
Technical Paper | doi.org/10.13182/NSE12-87
Articles are hosted by Taylor and Francis Online.
It is well known that the sample variance of a tally mean in Monte Carlo (MC) eigenvalue calculations is biased because of the intercycle correlations of the fission source distribution (FSD). This paper proposes the history-based batch method as a new method that can eliminate the dependency between samples and thereby estimate the real variance of the mean of the MC tally directly from routine cycle-by-cycle MC eigenvalue calculations. The new method estimates the real variance of the MC tally by the sample variance from tally estimates of the history-based batch defined as a set of histories with the same ancestor fission neutrons determined at the first active cycle MC run. The batch averages of the MC tally necessary for this estimate are obtained by correcting the individual tallies with the batch specific weight factors that are derived from independent FSD normalization of each individual batch. Diagnostic methods are also devised for small-batch-size problems, which one may encounter in applying the history-based batch method. The effectiveness of the history-based batch method is examined as a function of the dominance ratio and the batch size for the weakly coupled fissile array problems in comparison with those of bias estimation methods currently available. Its validity is also investigated in terms of the fuel storage facility problem exhibiting a slow source convergence.