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Division Spotlight
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Nuclear Science and Engineering
May 2025
Nuclear Technology
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April 2025
Latest News
Latest Red Book stresses need for boosts in uranium development
The latest edition of Uranium 2024: Resources, Production and Demand, commonly known as the Red Book, reports that current uranium resources are sufficient to meet low- and high-growth nuclear capacity needs through 2050 and beyond, but that further development of resources is still required. Even if nuclear capacity remains stable at 2050 levels through the end of the century, the report noted that cumulative demand “could exceed the current identified uranium resource base of nearly 8 million tonnes by the 2080s under the low-growth demand scenario and by the 2110s under the high-growth demand scenario outlined in this edition.”
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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