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Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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ARG-US Remote Monitoring Systems: Use Cases and Applications in Nuclear Facilities and During Transportation
As highlighted in the Spring 2024 issue of Radwaste Solutions, researchers at the Department of Energy’s Argonne National Laboratory are developing and deploying ARG-US—meaning “Watchful Guardian”—remote monitoring systems technologies to enhance the safety, security, and safeguards (3S) of packages of nuclear and other radioactive material during storage, transportation, and disposal.
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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
