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Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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Latest News
Senate committee hears from energy secretary nominee Chris Wright
Wright
Chris Wright, president-elect Trump’s pick to lead the U.S. Department of Energy, spent hours today fielding questions from members of the U.S. Senate’s committee on Energy and Natural Resources.
During the hearing, Wright—who’s spent most of his career in fossil fuels—made comments in support of nuclear energy and efforts to expand domestic generation in the near future. Asked what actions he would take as energy secretary to improve the development and deployment of SMRs, Wright said: “It’s a big challenge, and I’m new to government, so I can’t list off the five levers I can pull. But (I’ve been in discussions) about how to make it easier to research, to invest, to build things. The DOE has land at some of its facilities that can be helpful in this regard.”
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Vectorization of Transport and Diffusion Computations on the CDC Cyber 205
I. K. Abu-Shumays
Nuclear Science and Engineering | Volume 92 | Number 1 | January 1986 | Pages 4-19
Technical Paper | doi.org/10.13182/NSE86-A17859
Experience with the Incomplete Cholesky Conjugate Gradient Method in a Diffusion Code
Willi Hoebel
Nuclear Science and Engineering | Volume 92 | Number 1 | January 1986 | Pages 20-26
Technical Paper | doi.org/10.13182/NSE86-A17860
Performance of a Nonstationary Implicit Scheme for Solving Large Systems of Linear Equations
J. M. Barry, J. P. Pollard
Nuclear Science and Engineering | Volume 92 | Number 1 | January 1986 | Pages 27-33
Technical Paper | doi.org/10.13182/NSE86-A17861
Perturbation Theory Based on a Nodal Model
Temitope A. Taiwo, A. F. Henry
Nuclear Science and Engineering | Volume 92 | Number 1 | January 1986 | Pages 34-41
Technical Paper | doi.org/10.13182/NSE86-A17862
Numerical Solution of Neutron Diffusion Equations in Multiconnected Regions Using Compound Boundary-Fitted Coordinate Systems
Motoo Aoyama and Sadao Uchikawa
Nuclear Science and Engineering | Volume 92 | Number 1 | January 1986 | Pages 42-50
Technical Paper | doi.org/10.13182/NSE86-A17863
Diffusion Coefficient in Nonuniform Lattices
A. Dévényi, J. Gadó, A. Keresztúri, M. Makai
Nuclear Science and Engineering | Volume 92 | Number 1 | January 1986 | Pages 51-55
Technical Paper | doi.org/10.13182/NSE86-A17864
Application and Verification of the Simplified Equivalence Theory for Burnup States
K. Koebke, H. Haase, L. Hetzelt, H.-J. Winter
Nuclear Science and Engineering | Volume 92 | Number 1 | January 1986 | Pages 56-65
Technical Paper | doi.org/10.13182/NSE86-A17865
Use of a Dynamic Grid Adaptation in the Asymmetric Weighted Residual Method
U. Graf, P. Romstedt, W. Werner
Nuclear Science and Engineering | Volume 92 | Number 1 | January 1986 | Pages 66-70
Technical Paper | doi.org/10.13182/NSE86-A17866
Numerical Analysis of Critical Two-Phase Flow in a Convergent-Divergent Nozzle
P. Romstedt, W. Werner
Nuclear Science and Engineering | Volume 92 | Number 1 | January 1986 | Pages 71-83
Technical Paper | doi.org/10.13182/NSE86-A17867
Finite Element Solution of the Fokker-Plonck Equation in Electrostatic Magnetic Mirror Fusion Machines
Taha H. Zerguini
Nuclear Science and Engineering | Volume 92 | Number 1 | January 1986 | Pages 84-91
Technical Paper | doi.org/10.13182/NSE86-A17868
A One-Dimensional Hybrid Code for Field-Reversed Mirror Dynamics
R. A. Stark, G. H. Miley
Nuclear Science and Engineering | Volume 92 | Number 1 | January 1986 | Pages 92-97
Technical Paper | doi.org/10.13182/NSE86-A17869
A Linear Discontinuous Galerkin Approximation for the Continuous Slowing Down Operator
Maximo S. Lazo, J. E. Morel
Nuclear Science and Engineering | Volume 92 | Number 1 | January 1986 | Pages 98-109
Technical Paper | doi.org/10.13182/NSE86-A17870
Electron Transport Calculational Methods for a Plane Source Embedded in an Infinite Medium
S. Woolf, W. L. Filippone, B. D. Ganapol, J. C. Garth
Nuclear Science and Engineering | Volume 92 | Number 1 | January 1986 | Pages 110-118
Technical Paper | doi.org/10.13182/NSE86-A17871
Semi-Implicit Method for Three-Dimensional Resistive Magnetohydrodynamic Simulation of Fusion Plasmas
Douglas S. Harned, W. Kerner
Nuclear Science and Engineering | Volume 92 | Number 1 | January 1986 | Pages 119-125
Technical Paper | doi.org/10.13182/NSE86-A17872
Vectorization of the Light Water Reactor Transient Analysis Code RELAP5
Misako Ishiguro and Hiroo Harada, Naohisa Shinozawa and Ken-itsu Naraoka
Nuclear Science and Engineering | Volume 92 | Number 1 | January 1986 | Pages 126-135
Technical Paper | doi.org/10.13182/NSE86-A17873
Numerical Experiments in Concurrent Multiprocessing with the RELAP5 Nuclear Reactor Systems Code
H. Makowitz
Nuclear Science and Engineering | Volume 92 | Number 1 | January 1986 | Pages 136-143
Technical Paper | doi.org/10.13182/NSE86-A17874
Boiling Water Reactor Plant Analyzer Development at Brookhaven National Laboratory
H. S. Cheng, W. Wulff, A. N. Mallen, S. V. Lekach, A. Stritar, R. J. Cerbone
Nuclear Science and Engineering | Volume 92 | Number 1 | January 1986 | Pages 144-156
Technical Paper | doi.org/10.13182/NSE86-A17875
Solution of Large Unsymmetric Eigensystems for Fluid/Structure Interaction Problems
I.-W. Yu
Nuclear Science and Engineering | Volume 92 | Number 1 | January 1986 | Pages 157-161
Technical Paper | doi.org/10.13182/NSE86-A17876
A Method of Computing Hydraulic Reaction Force Due to a Fluid Jet at a Steamline Break
S. Abedin, K. Takeuchi, M. Y. Young
Nuclear Science and Engineering | Volume 92 | Number 1 | January 1986 | Pages 162-169
Technical Paper | doi.org/10.13182/NSE86-A17877
An Advanced Multidimensional Method for Structural and Hydrodynamic Analysis of Liquid-Metal Fast Breeder Reactor Piping Systems
C. Y. Wang, W. R. Zeuch
Nuclear Science and Engineering | Volume 92 | Number 1 | January 1986 | Pages 170-177
Technical Paper | doi.org/10.13182/NSE86-A17878
Projected Discrete Ordinates Methods for Numerical Transport Problems
Edward W. Larsen
Nuclear Science and Engineering | Volume 92 | Number 2 | February 1986 | Pages 179-185
Technical Paper | doi.org/10.13182/NSE86-A18163
Nonlinear Diffusion Synthetic Acceleration Difference Schemes for Radiative Transfer Applications
Bradley A. Clark
Nuclear Science and Engineering | Volume 92 | Number 2 | February 1986 | Pages 186-191
Technical Paper | doi.org/10.13182/NSE86-A18164
Augmented Weighted-Diamond Form of the Linear-Nodal Scheme for Cartesian Coordinate Systems
Wallace F. Walters
Nuclear Science and Engineering | Volume 92 | Number 2 | February 1986 | Pages 192-196
Technical Paper | doi.org/10.13182/NSE86-A18165
Discontinuous Finite Element Method for Solving the Two-Dimesional Neutron Transport Equation on Lagrangian Meshes
G. Samba
Nuclear Science and Engineering | Volume 92 | Number 2 | February 1986 | Pages 197-203
Technical Paper | doi.org/10.13182/NSE86-A18166
Finite Element Formulations of Nodal Schemes for Neutron Diffusion and Transport Problems
E. Del Valle, J. P. Hennart, D. Meade
Nuclear Science and Engineering | Volume 92 | Number 2 | February 1986 | Pages 204-211
Technical Paper | doi.org/10.13182/NSE86-A18167
The DCN-SN Hybrid Method for Neutron Transport Calculations in (r-z) Geometry
Yoichi Watanabe and Charles W. Maynard
Nuclear Science and Engineering | Volume 92 | Number 2 | February 1986 | Pages 212-217
Technical Paper | doi.org/10.13182/NSE86-A18168
Linear Discontinuous Finite Elements for Phase-Space Multidimensional Transport Calculations
M. Mordant
Nuclear Science and Engineering | Volume 92 | Number 2 | February 1986 | Pages 218-227
Technical Paper | doi.org/10.13182/NSE86-A18169
Use of Multidimensional Transport Methodology on Nuclear Logging Problems
John J. Ullo
Nuclear Science and Engineering | Volume 92 | Number 2 | February 1986 | Pages 228-239
Technical Paper | doi.org/10.13182/NSE86-A18170
Interface Current Method for Cluster Geometry
G. Marleau, A. Hébert
Nuclear Science and Engineering | Volume 92 | Number 2 | February 1986 | Pages 240-246
Technical Paper | doi.org/10.13182/NSE86-A18171
A Transport Multicell Method for Two-Dimensional Lattices of Hexagonal Cells
Richard Sanchez
Nuclear Science and Engineering | Volume 92 | Number 2 | February 1986 | Pages 247-254
Technical Paper | doi.org/10.13182/NSE86-A18172
Refinement of the Substructure Method for Integral Transport Calculations
Žarko Stankovski
Nuclear Science and Engineering | Volume 92 | Number 2 | February 1986 | Pages 255-260
Technical Paper | doi.org/10.13182/NSE86-A18173
A Generalization of the Livolant-Jeanpierre Theory for Resonance Absorption Calculation
P. Reuss
Nuclear Science and Engineering | Volume 92 | Number 2 | February 1986 | Pages 261-266
Technical Paper | doi.org/10.13182/NSE86-A18174
Internal Interface Perturbations: Calculational Method Using the Eigenvalue Innplicit Expansion of the Conditioned Problem
J. Porta, J. Y. Doriath, B. Martinet
Nuclear Science and Engineering | Volume 92 | Number 2 | February 1986 | Pages 267-271
Technical Paper | doi.org/10.13182/NSE86-A18175
Solution of the One-Group Time-Dependent Neutron Transport Equation in an Infinite Medium by Polynomial Reconstruction
B. D. Ganapol
Nuclear Science and Engineering | Volume 92 | Number 2 | February 1986 | Pages 272-279
Technical Paper | doi.org/10.13182/NSE86-A18176
Monte Carlo Techniques for Analyzing Deep-Penetration Problems
S. N. Cramer, J. Gonnord, J. S. Hendricks
Nuclear Science and Engineering | Volume 92 | Number 2 | February 1986 | Pages 280-288
Technical Paper | doi.org/10.13182/NSE86-A18177
Review of Monte Carlo Techniques for Analyzing Reactor Perturbations
H. Rief, E. M. Gelbard, R. W. Schaefer, K. S. Smith
Nuclear Science and Engineering | Volume 92 | Number 2 | February 1986 | Pages 289-297
Technical Paper | doi.org/10.13182/NSE86-A18178
Vectorization of the KENO-IV Code
Kiyoshi Asai, Kenji Higuchi, and Jun-ichi Katakura, Yutaka Kurita
Nuclear Science and Engineering | Volume 92 | Number 2 | February 1986 | Pages 298-307
Technical Paper | doi.org/10.13182/NSE86-A18179
Thermal-Hydraulic Methods in Fast Reactor Safety
David P. Weber and Laural L. Briggs
Nuclear Science and Engineering | Volume 92 | Number 2 | February 1986 | Pages 308-329
Technical Paper | doi.org/10.13182/NSE86-A18180
On Trial Functions in the Nested Element Method
D. V. Altiparmakov
Nuclear Science and Engineering | Volume 92 | Number 2 | February 1986 | Pages 330-337
Technical Paper | doi.org/10.13182/NSE86-A18181
On the Solution of the Inverse Problem of Radiation Scattering Imaging
E. M. A. Hussein, D. A. Meneley, S. Banerjee
Nuclear Science and Engineering | Volume 92 | Number 3 | March 1986 | Pages 341-349
Technical Paper | doi.org/10.13182/NSE86-A17524
Fast Neutron Inelastic Scattering Cross Sections of 238U for States Between 680 and 1530 keV
J. Q. Shao, G. P. Couchell, J. J. Egan, G. H. R. Kegel, S. Q. Li, A. Mittler, D. J. Pullen, W. A. Schier, E. D. Arthur
Nuclear Science and Engineering | Volume 92 | Number 3 | March 1986 | Pages 350-371
Technical Paper | doi.org/10.13182/NSE86-A17525
A Three-Dimensional Neutronics Model for Reactor Training Simulators
M. V. Gregory, B. N. Aviles, S. J. Yakura
Nuclear Science and Engineering | Volume 92 | Number 3 | March 1986 | Pages 372-381
Technical Paper | doi.org/10.13182/NSE86-A17526
The Transport of 14-MeV Neutrons Through Heavy Materials 150 < A < 208
L. F. Hansen, H. M. Blann, R. J. Howerton, T. T. Komoto, B. Pohl
Nuclear Science and Engineering | Volume 92 | Number 3 | March 1986 | Pages 382-396
Technical Paper | doi.org/10.13182/NSE86-A17527
Spherical Harmonics Method for a Two-Dimensional Multigroup Transport Equation Using a Semi-Discrete Ordinates Equation: Part I
Keisuke Kobayashi
Nuclear Science and Engineering | Volume 92 | Number 3 | March 1986 | Pages 397-406
Technical Paper | doi.org/10.13182/NSE86-A17528
Spherical Harmonics Method for a Two-Dimensional Multigroup Transport Equation Using a Semi-Discrete Ordinates Equation: Part II
Keisuke Kobayashi and Tsuyoshi Misawa
Nuclear Science and Engineering | Volume 92 | Number 3 | March 1986 | Pages 407-420
Technical Paper | doi.org/10.13182/NSE86-A17529
Analytic Solution of the Spencer-Lewis Angular-Spatial Moments Equations
W. L. Filippone
Nuclear Science and Engineering | Volume 92 | Number 3 | March 1986 | Pages 421-439
Technical Paper | doi.org/10.13182/NSE86-A17530
Simplified Spin Cutoff Factors for Particle-Hole Level Densities in Precompound Nuclear Reaction Theory
C. Y. Fu
Nuclear Science and Engineering | Volume 92 | Number 3 | March 1986 | Pages 440-453
Technical Paper | doi.org/10.13182/NSE86-A17531
Construction of Adjoint Operators for Coupled Equations Depending on Different Variables
J. E. Hoogenboom
Nuclear Science and Engineering | Volume 92 | Number 3 | March 1986 | Pages 454-458
Technical Note | doi.org/10.13182/NSE86-A17532
The Inelastic Scattering of Neutrons by 232Th
A.M. Street, P.E. Hodgson
Nuclear Science and Engineering | Volume 92 | Number 3 | March 1986 | Pages 459-464
Technical Note | doi.org/10.13182/NSE86-A17533
A Monte Carlo Learning/Biasing Experiment with Intelligent Random Numbers
Thomas E. Booth
Nuclear Science and Engineering | Volume 92 | Number 3 | March 1986 | Pages 465-481
Technical Note | doi.org/10.13182/NSE86-A17534
Analytical Results of Variance Reduction Characteristics of Biased Monte Carlo for Deep-Penetration Problems
K. P. N. Murthy, R. Indira
Nuclear Science and Engineering | Volume 92 | Number 3 | March 1986 | Pages 482-487
Technical Note | doi.org/10.13182/NSE86-A17535
Helium Production in Pure Elements, Isotopes, and Alloy Steels by 14.8-MeV Neutrons
D. W. Kneff, B. M. Oliver., Harry Farrar IV, L. R. Greenwood
Nuclear Science and Engineering | Volume 92 | Number 4 | April 1986 | Pages 491-524
Technical Paper | doi.org/10.13182/NSE86-A18608
Neutron Transmission Measurement and Resonance Analysis of 93Zr from 60 to 6000 eV
R. L. Macklin, J. A. Harvey, N. W. Hill
Nuclear Science and Engineering | Volume 92 | Number 4 | April 1986 | Pages 525-530
Technical Paper | doi.org/10.13182/NSE86-A18609
Optimal Control of a Boiling Water Reactor in Load-Following via Multilevel Methods
Chaung Lin,Lawrence M. Grossman
Nuclear Science and Engineering | Volume 92 | Number 4 | April 1986 | Pages 531-544
Technical Paper | doi.org/10.13182/NSE86-A18610
Biasing Parameter Limits for Synergistic Monte Carlo in Deep-Penetration Calculations
S. R. Dwivedi, H. C. Gupta
Nuclear Science and Engineering | Volume 92 | Number 4 | April 1986 | Pages 545-549
Technical Paper | doi.org/10.13182/NSE86-A18611
Two-Parametric Presentation of Thermal Neutron Flux in Infinite Hydrogenous Media
D. Ingman, E. Taviv
Nuclear Science and Engineering | Volume 92 | Number 4 | April 1986 | Pages 550-569
Technical Paper | doi.org/10.13182/NSE86-A18612
Radiation Transfer in a Cylindrical Vessel Containing High-Temperature Corium Aerosols
M. P. Mengüç, R. Viskanta
Nuclear Science and Engineering | Volume 92 | Number 4 | April 1986 | Pages 570-583
Technical Paper | doi.org/10.13182/NSE86-A18613
Monte Carlo and Discrete Ordinates Calculations of 14-MeV Neutrons Streaming Through a Stainless Steel Duct: Comparison with Experiment I
R. T. Santoro, J. M. Barnes,R. G. Alsmiller, Jr.,J. D. Drischler
Nuclear Science and Engineering | Volume 92 | Number 4 | April 1986 | Pages 584-595
Technical Notes | doi.org/10.13182/NSE86-A18614
Gamma-Ray Energy Deposition Measurements in the Fast Breeder Blanket Facility
K. R. Koch, F. M. Clikeman,R. H. Johnson
Nuclear Science and Engineering | Volume 92 | Number 4 | April 1986 | Pages 596-605
Technical Notes | doi.org/10.13182/NSE86-A18615