ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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!
Latest Magazine Issues
Jul 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
August 2025
Fusion Science and Technology
Latest News
Remembering ANS member Gil Brown
Brown
The nuclear community is mourning the loss of Gilbert Brown, who passed away on July 11 at the age of 77 following a battle with cancer.
Brown, an American Nuclear Society Fellow and an ANS member for nearly 50 years, joined the faculty at Lowell Technological Institute—now the University of Massachusetts–Lowell—in 1973 and remained there for the rest of his career. He eventually became director of the UMass Lowell nuclear engineering program. After his retirement, he remained an emeritus professor at the university.
Sukesh Aghara, chair of the Nuclear Engineering Department Heads Organization, noted in an email to NEDHO members and others that “Gil was a relentless advocate for nuclear energy and a deeply respected member of our professional community. He was also a kind and generous friend—and one of the reasons I ended up at UMass Lowell. He served the university with great dedication. . . . Within NEDHO, Gil was a steady presence and served for many years as our treasurer. His contributions to nuclear engineering education and to this community will be dearly missed.”
Jump to:
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