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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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
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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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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
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A Liquid-Metal Reactor for Burning Minor Actinides of Spent Light Water Reactor Fuel - I: Neutronics Design Study
Hangbok Choi, Thomas J. Downar
Nuclear Science and Engineering | Volume 133 | Number 1 | September 1999 | Pages 1-22
Technical Paper | doi.org/10.13182/NSE99-A2069
A Liquid-Metal Reactor for Burning Minor Actinides of Spent Light Water Reactor Fuel - II: Nuclear Data Uncertainty Analysis
Nuclear Science and Engineering | Volume 133 | Number 1 | September 1999 | Pages 23-39
Technical Paper | doi.org/10.13182/NSE99-A2070
Improved Discrete Ordinates Calculations for an Approximate Model of Neutral Particle Transport in Ducts
Roberto D. M. Garcia, Shizuca Ono
Nuclear Science and Engineering | Volume 133 | Number 1 | September 1999 | Pages 40-54
Technical Paper | doi.org/10.13182/NSE99-1
A Midway Forward-Adjoint Coupling Method for Neutron and Photon Monte Carlo Transport
I. V. Serov, T. M. John, J. E. Hoogenboom
Nuclear Science and Engineering | Volume 133 | Number 1 | September 1999 | Pages 55-72
Technical Paper | doi.org/10.13182/NSE99-A2072
Monte Carlo Methods for Flux Expansion Solutions of Transport Problems
Jerome Spanier
Nuclear Science and Engineering | Volume 133 | Number 1 | September 1999 | Pages 73-79
Technical Paper | doi.org/10.13182/NSE99-A2073
Monte Carlo Simulation of Neutron Porosity Oil Well Logging Tools: Combining the Geometry-Independent Fine-Mesh Importance Map and One-Dimensional Diffusion Model Approaches
Robin P. Gardner, Lianyan Liu
Nuclear Science and Engineering | Volume 133 | Number 1 | September 1999 | Pages 80-91
Technical Paper | doi.org/10.13182/NSE99-A2074
Numerical Simulation of Gas-Liquid Two-Phase Flow Around a Rectangular Cylinder by the Incompressible Two-Fluid Model
Tomomi Uchiyama
Nuclear Science and Engineering | Volume 133 | Number 1 | September 1999 | Pages 92-105
Technical Note | doi.org/10.13182/NSE99-A2075
Low-Flow Onset of Flow Instability in Heated Microchannels
G. M. Roach, Jr., S. I. Abdel-Khalik, S. M. Ghiaasiaan, M. F. Dowling, S. M. Jeter
Nuclear Science and Engineering | Volume 133 | Number 1 | September 1999 | Pages 106-117
Technical Note | doi.org/10.13182/NSE99-A2076
Decomposition Principle for Refueling Optimization in Fast Breeder Reactors
Yasuyoshi Kato, Motomi Odamura, Hiroshi Urushihara, Hidesuke Matsushima
Nuclear Science and Engineering | Volume 133 | Number 2 | October 1999 | Pages 119-146
Technical Paper | doi.org/10.13182/NSE99-A2077
Analytical Calculation of the Average Dancoff Factor for a Fuel Kernel in a Pebble Bed High-Temperature Reactor
E. E. Bende, A. H. Hogenbirk, J. L. Kloosterman, H. van Dam
Nuclear Science and Engineering | Volume 133 | Number 2 | October 1999 | Pages 147-162
Technical Paper | doi.org/10.13182/NSE99-A2078
Applications of Monte Carlo Simulations of Thermalization Processes to the Nondestructive Assay of Graphite
Felix C. Difilippo
Nuclear Science and Engineering | Volume 133 | Number 2 | October 1999 | Pages 163-177
Technical Paper | doi.org/10.13182/NSE99-2
Experimental Installation for Radioecology Research on Defined Ecosystems Subjected to Contamination in Controlled Conditions
C. Madoz-Escande, F. Bréchignac, C. Colle, E. Dubois, J. Hugon, H. Jouglet, M. Moutier, P. Rongier, A. Sanchez, E. H. Schulte, R. Zanon
Nuclear Science and Engineering | Volume 133 | Number 2 | October 1999 | Pages 178-191
Technical Paper | doi.org/10.13182/NSE99-A2080
A Mesh-Free Numerical Method for Direct Simulation of Gas-Liquid Phase Interface
Han Young Yoon, Seiichi Koshizuka, Yoshiaki Oka
Nuclear Science and Engineering | Volume 133 | Number 2 | October 1999 | Pages 192-200
Technical Paper | doi.org/10.13182/NSE99-A2081
A Two-Dimensional Intranodal Flux Expansion Method for Hexagonal Geometry
Ulrich Grundmann, Frank Hollstein
Nuclear Science and Engineering | Volume 133 | Number 2 | October 1999 | Pages 201-212
Technical Paper | doi.org/10.13182/NSE99-A2082
Shift and Adjusted Reference Temperature for a Boiling Water Reactor Vessel
L. C. Longoria, J. C. Palacios, J. Santos
Nuclear Science and Engineering | Volume 133 | Number 2 | October 1999 | Pages 213-217
Technical Paper | doi.org/10.13182/NSE99-A2083
Model Calculation of n + 12C Reactions from 4.8 to 20 MeV
Jingshang Zhang, Yinlu Han, Ligang Cao
Nuclear Science and Engineering | Volume 133 | Number 2 | October 1999 | Pages 218-234
Technical Paper | doi.org/10.13182/NSE98-100
Resonance Parameter Adjustment Methodology Based on Integral Experiment Analysis
Patrick Blaise, Eric Fort
Nuclear Science and Engineering | Volume 133 | Number 3 | November 1999 | Pages 235-257
Technical Paper | doi.org/10.13182/NSE99-A2085
Exponential Convergence Rates for Reduced-Source Monte Carlo Transport in [x,] Geometry
Henry Lichtenstein
Nuclear Science and Engineering | Volume 133 | Number 3 | November 1999 | Pages 258-268
Technical Paper | doi.org/10.13182/NSE99-A2086
The Backward Theory of Feynman- and Rossi-Alpha Methods with Multiple Emission Sources
I. Pázsit, Y. Yamane
Nuclear Science and Engineering | Volume 133 | Number 3 | November 1999 | Pages 269-281
Technical Paper | doi.org/10.13182/NSE99-A2087
Subcriticality-Level Evaluation in Accelerator-Driven Systems by Harmonic Modulation of the External Source
M. Carta, A. D'Angelo
Nuclear Science and Engineering | Volume 133 | Number 3 | November 1999 | Pages 282-292
Technical Paper | doi.org/10.13182/NSE99-A2088
System Structure Identification by Neural Networks: Application to the Thermal-Hydraulic Correlations in a Steam Generator
M. Marseguerra, F. Mazzarella
Nuclear Science and Engineering | Volume 133 | Number 3 | November 1999 | Pages 293-300
Technical Paper | doi.org/10.13182/NSE99-A2089
Fuel-Containing Masses of Chernobyl Unit 4: Multiplying Properties and Neutron Characteristics
Vladimir A. Babenko, Laszlo L. Jenkovszky, Volodymyr A. Romanov, Volodymyr N. Pavlovych, Oleg Ya. Vertsimakha
Nuclear Science and Engineering | Volume 133 | Number 3 | November 1999 | Pages 301-313
Technical Paper | doi.org/10.13182/NSE99-A2090
The Inversion Point of the Isothermal Reactivity Coefficient of the IPEN/MB-01 Reactor - 1: Experimental Procedure
A. dos Santos, H. Pasqualeto, L. C. C. B. Fanaro, R. Fuga, R. Jerez
Nuclear Science and Engineering | Volume 133 | Number 3 | November 1999 | Pages 314-326
Technical Paper | doi.org/10.13182/NSE99-A2091
Calculated Excitation Functions of Proton-Induced Reactions on Vanadium and Chromium for Incident Energies up to 30 MeV
Xiaoping Xu, Yinlu Han, Youxiang Zhuang
Nuclear Science and Engineering | Volume 133 | Number 3 | November 1999 | Pages 327-334
Technical Paper | doi.org/10.13182/NSE99-A2092
Experimental Determination of Detection Limits for Performing Neutron Activation Analysis for Gold in the Field
Mark S. Jarzemba, James Weldy, English Pearcy, Jim Prikryl, David Pickett
Nuclear Science and Engineering | Volume 133 | Number 3 | November 1999 | Pages 335-341
Technical Paper | doi.org/10.13182/NSE99-A2093
Tritium Production Rate and Tritium Breeding Ratio: A Comparative Study of Li2O and Lithium Assemblies with Different Concentrations of 6Li
Manasi Goswami, Sanjay Gupta, Feroz Ahmed
Nuclear Science and Engineering | Volume 133 | Number 3 | November 1999 | Pages 342-349
Technical Note | doi.org/10.13182/NSE99-A2094
A Discrete Ordinates Nodal Method for One-Dimensional Neutron Transport Calculation in Curvilinear Geometries
Yican Wu, Zhongsheng Xie, Ulrich Fischer
Nuclear Science and Engineering | Volume 133 | Number 3 | November 1999 | Pages 350-357
Technical Note | doi.org/10.13182/NSE99-A2095