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NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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.
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Analytical, Semi-Analytical, and Numerical Heavy-Gas Verification Benchmarks of the Effective Multiplication Factor and Temperature Coefficient
Matthew A. Gonzales, Brian C. Kiedrowski, Anil K. Prinja, Forrest B. Brown
Nuclear Science and Engineering | Volume 191 | Number 1 | July 2018 | Pages 1-45
Technical Paper | doi.org/10.1080/00295639.2018.1442546
Modeling of Resonance-Interference Effect in Depleted Fuel Compositions by Pseudo Resonant Isotopes
Qian Zhang, Qiang Zhao, Won Sik Yang, Hongchun Wu
Nuclear Science and Engineering | Volume 191 | Number 1 | July 2018 | Pages 46-65
Technical Paper | doi.org/10.1080/00295639.2018.1429174
Acropolis: Novel Approach to Single-Pin Depletion Calculations Using Stochastic Optimization
Lubomír Bureš, Stefano Caruso
Nuclear Science and Engineering | Volume 191 | Number 1 | July 2018 | Pages 66-84
Technical Paper | doi.org/10.1080/00295639.2018.1442059
Investigation on the Neutron Transmission of B4C/CF/PI/AA6061 Hybrid Composite Laminates: Experimental and Numerical Simulation Results
Xuelong Fu, Zhengbo Ji, Chunbo Li
Nuclear Science and Engineering | Volume 191 | Number 1 | July 2018 | Pages 85-97
Technical Paper | doi.org/10.1080/00295639.2018.1449492
Total Ionizing Dose Effects of SiGe HBTs Induced by 60Co Gamma-Ray Irradiation
Shu-Huan Liu, Aqil Hussain, Da Li, Xiaoqiang Guo, Zhuo-Qi Li, Olarewaju Mubashiru Lawal, Jiangkun Yang, Wei Chen
Nuclear Science and Engineering | Volume 191 | Number 1 | July 2018 | Pages 98-103
Technical Paper | doi.org/10.1080/00295639.2018.1450004
Discontinuous Finite Element Quasi-Diffusion Methods
Dmitriy Y. Anistratov, James S. Warsa
Nuclear Science and Engineering | Volume 191 | Number 2 | August 2018 | Pages 105-120
Technical Paper | doi.org/10.1080/00295639.2018.1450013
Discrete Eigenvalues of Case Spectrum with Anisotropic Scattering
D. C. Sahni, R. G. Tureci
Nuclear Science and Engineering | Volume 191 | Number 2 | August 2018 | Pages 121-135
Technical Paper | doi.org/10.1080/00295639.2018.1463748
Convergence Studies on Nonlinear Coarse-Mesh Finite Difference Accelerations for Neutron Transport Analysis
Hyeon Tae Kim, Yonghee Kim
Nuclear Science and Engineering | Volume 191 | Number 2 | August 2018 | Pages 136-149
Technical Paper | doi.org/10.1080/00295639.2018.1463747
Activation Measurements of Cross Sections for Ground and Isomeric States Production in Neutron Threshold Reactions on Y and Au
P. Chudoba, A. Krása, J. Vrzalová, O. Svoboda, S. Kilim, V. Wagner, M. Majerle, M. Štefánik, M. Suchopár, A. Kugler, M. Bielewicz, E. Strugalska-Gola, M. Szuta
Nuclear Science and Engineering | Volume 191 | Number 2 | August 2018 | Pages 150-160
Technical Paper | doi.org/10.1080/00295639.2018.1455437
Studies on Reactivity Coefficients of Thorium-Based Fuel (Th-233U)O2 with Molten Salt (Flibe) Cooled Pebble
Indrajeet Singh, Anurag Gupta, Umasankari Kannan
Nuclear Science and Engineering | Volume 191 | Number 2 | August 2018 | Pages 161-177
Technical Note | doi.org/10.1080/00295639.2018.1463745
Concept of Stationary Wave Reactor with Rotational Fuel Shuffling
Kazuki Kuwagaki, Jun Nishiyama, Toru Obara
Nuclear Science and Engineering | Volume 191 | Number 2 | August 2018 | Pages 178-186
Technical Note | doi.org/10.1080/00295639.2018.1463744
MULTI-PRED: A Software Module for Predictive Modeling of Coupled Multi-Physics Systems
Dan G. Cacuci, Ruixian Fang, Madalina C. Badea
Nuclear Science and Engineering | Volume 191 | Number 2 | August 2018 | Pages 187-202
Computer Code Abstract | doi.org/10.1080/00295639.2018.1451675
A Review of Molten Salt Reactor Kinetics Models
Daniel Wooten, Jeffrey J. Powers
Nuclear Science and Engineering | Volume 191 | Number 3 | September 2018 | Pages 203-230
Critical Review | doi.org/10.1080/00295639.2018.1480182
Singular Eigenfunction Expansion Solution for Time-Dependent Neutron Transport with Delayed Neutrons
Jeffery D. Densmore
Nuclear Science and Engineering | Volume 191 | Number 3 | September 2018 | Pages 231-247
Technical Paper | doi.org/10.1080/00295639.2018.1466542
Variance Estimation in Monte Carlo Eigenvalue Simulations Using Spectral Analysis Method
Lei Jin, Kaushik Banerjee
Nuclear Science and Engineering | Volume 191 | Number 3 | September 2018 | Pages 248-261
Technical Paper | doi.org/10.1080/00295639.2018.1471269
Calculation and Evaluations for n+64,66,67,68,70,natZn Reactions
Jiaqi Hu, Yongli Xu, Yinlu Han
Nuclear Science and Engineering | Volume 191 | Number 3 | September 2018 | Pages 262-281
Technical Paper | doi.org/10.1080/00295639.2018.1469334
Investigation of (n, α) Reaction Cross Sections for a Number of Structural Material Isotopes
Tatiana Khromyleva, Ivan Bondarenko, Alexander Gurbich, Vladimir Ketlerov, Vitaly Khryachkov, Pavel Prusachenko
Nuclear Science and Engineering | Volume 191 | Number 3 | September 2018 | Pages 282-290
Technical Paper | doi.org/10.1080/00295639.2018.1463746
Developing a Full-Core MCNP6 and RELAP5 Model of the European Pressurized Reactor Using NWURCS
Maria Hendrina Du Toit, Vishana Vivian Naicker
Nuclear Science and Engineering | Volume 191 | Number 3 | September 2018 | Pages 291-304
Computer Code Abstract | doi.org/10.1080/00295639.2018.1468153