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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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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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Wyoming OKs construction of TerraPower’s Natrium plant
Progress continues for TerraPower’s Natrium plant, with the latest win coming in the form of a state permit for construction of nonnuclear portions of the advanced reactor.
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Iterative and Direct Approaches to the Critical Dominant Eigenfunction in Three-Dimensional Neutron Transport
F. Premuda, G. Spiga
Nuclear Science and Engineering | Volume 63 | Number 1 | May 1977 | Pages 1-8
Technical Paper | doi.org/10.13182/NSE77-A26998
Monte Carlo Treatment of Fundamental-Mode Neutron Leakage in the Presence of Voids
Ely M. Gelbard, Richard Lell
Nuclear Science and Engineering | Volume 63 | Number 1 | May 1977 | Pages 9-23
Technical Paper | doi.org/10.13182/NSE77-A26999
Neutron Wave Propagation Across a Temperature Discontinuity
Ashok Kumar, N. K. Saxena, L. S. Kothari
Nuclear Science and Engineering | Volume 63 | Number 1 | May 1977 | Pages 24-30
Technical Paper | doi.org/10.13182/NSE77-A27000
Neutron Kinetics of Highly Compressed Fissionable Pellets
J. Ligou
Nuclear Science and Engineering | Volume 63 | Number 1 | May 1977 | Pages 31-40
Technical Paper | doi.org/10.13182/NSE77-A27001
Origin of Protons in Californium-252 Fission
John A. Adams, R. R. Roy
Nuclear Science and Engineering | Volume 63 | Number 1 | May 1977 | Pages 41-47
Technical Paper | doi.org/10.13182/NSE77-A27002
Neutron and Gamma Radiation from a Nitrogen Sphere Surrounding a D-T Neutron Source
G. S. Sidhu, W. E. Farley, L. F. Hansen, T. Komoto, B. Pohl, C. Wong
Nuclear Science and Engineering | Volume 63 | Number 1 | May 1977 | Pages 48-54
Technical Paper | doi.org/10.13182/NSE77-A27003
A Comparison of the Gamma-Ray Spectra from 2.8-keV Neutron Capture and Thermal-Neutron Capture in Sodium-23
W. M. Wilson, H. E. Jackson, G. E. Thomas
Nuclear Science and Engineering | Volume 63 | Number 1 | May 1977 | Pages 55-62
Technical Paper | doi.org/10.13182/NSE77-A27004
Structure-Fluid Interaction Between a Vibrating Wall and Flow in a Channel
R. A. Bajura, A. H. Mace, Jr.
Nuclear Science and Engineering | Volume 63 | Number 1 | May 1977 | Pages 63-74
Technical Paper | doi.org/10.13182/NSE77-A27005
Steady-State Natural Circulation Performance of the Experimental Breeder Reactor II Primary Heat Transport Circuit
Ralph M. Singer, Jerry L. Gillette, Gerald H. Golden, Dale Mohr, Wayne K. Lehto, Charles C. Price, John I. Sackett
Nuclear Science and Engineering | Volume 63 | Number 1 | May 1977 | Pages 75-82
Technical Paper | doi.org/10.13182/NSE77-A27006
The Effect of Niobium Additions on the Corrosion Behavior of Zircaloy-4
G. P. Sabol, S. G. McDonald
Nuclear Science and Engineering | Volume 63 | Number 1 | May 1977 | Pages 83-90
Technical Paper | doi.org/10.13182/NSE77-A27007
Selection of Angular Quadrature for Anisotropic Transport Computations
Wayne J. Mikols, J. Kenneth Shultis
Nuclear Science and Engineering | Volume 63 | Number 1 | May 1977 | Pages 91-95
Technical Note | doi.org/10.13182/NSE77-A27008
On the Inverse Problem for Multigroup Neutron Transport Theory
C. E. Siewert, M. N. Özişik, Y. Yener
Nuclear Science and Engineering | Volume 63 | Number 1 | May 1977 | Pages 95-96
Technical Note | doi.org/10.13182/NSE77-A27009
Rapid Method of Calculating the Fluence and Spectrum of Neutrons from a Critical Assembly and the Resulting Dose
Joseph Bessis
Nuclear Science and Engineering | Volume 63 | Number 1 | May 1977 | Pages 96-101
Technical Note | doi.org/10.13182/NSE77-A27010
Neutron-Induced Gamma-Ray Production in Lead-208 for Incident-Neutron Energies Between 4.9 and 8.0 MeV and in Bismuth-209 for an Incident-Neutron Energy of 5.4 MeV
J. K. Dickens
Nuclear Science and Engineering | Volume 63 | Number 1 | May 1977 | Pages 101-109
Technical Note | doi.org/10.13182/NSE77-A27011
Natural Convection in Porous Media with Heat Generation
H. C. Hardee, R. H. Nilson
Nuclear Science and Engineering | Volume 63 | Number 2 | June 1977 | Pages 119-132
Technical Paper | doi.org/10.13182/NSE77-A27015
Release of Adsorbed Krypton and Xenon from Spilled Charcoal
Dwight W. Underhill
Nuclear Science and Engineering | Volume 63 | Number 2 | June 1977 | Pages 133-142
Technical Paper | doi.org/10.13182/NSE77-A27016
Neutron Capture Cross Section of Plutonium-240
L. W. Weston, J. H. Todd
Nuclear Science and Engineering | Volume 63 | Number 2 | June 1977 | Pages 143-148
Technical Paper | doi.org/10.13182/NSE77-A27017
A Measurement of the Fission Cross Section of Plutonium-241 from 8 eV to 70 keV
G. W. Carlson, J. W. Behrens, J. B. Czirr
Nuclear Science and Engineering | Volume 63 | Number 2 | June 1977 | Pages 149-152
Technical Paper | doi.org/10.13182/NSE77-A27018
Measurement of the Uranium-238 Subthreshold Fission Cross Section for Incident Neutron Energies Between 0.6 and 100 keV
F. C. Difilippo, R. B. Perez, G. de Saussure, D. K. Olsen, R. W. Ingle
Nuclear Science and Engineering | Volume 63 | Number 2 | June 1977 | Pages 153-166
Technical Paper | doi.org/10.13182/NSE77-A27019
Solution of the Finite Element Diffusion and P1 Equations by Iteration
E. T. Tomlinson, J. C. Robinson
Nuclear Science and Engineering | Volume 63 | Number 2 | June 1977 | Pages 167-178
Technical Paper | doi.org/10.13182/NSE77-A27020
Exponential Supplementary Equations for SN Methods: The One-Dimensional Case
P. Barbucci, F. Di Pasquantonio
Nuclear Science and Engineering | Volume 63 | Number 2 | June 1977 | Pages 179-187
Technical Paper | doi.org/10.13182/NSE77-A27021
Laminar Heat Transfer Data with a Step-Varying Wall Heat Flux
Otto I. Reisman, Robert O. Parker
Nuclear Science and Engineering | Volume 63 | Number 2 | June 1977 | Pages 188-191
Technical Note | doi.org/10.13182/NSE77-A27022
The Trapping Efficiency of Molten Lithium for 20-keV Tritium Ions
Albert K. Fischer, David V. Steidl, Charles E. Brient, Fred A. Cafasso, Carl E. Johnson
Nuclear Science and Engineering | Volume 63 | Number 2 | June 1977 | Pages 191-193
Technical Note | doi.org/10.13182/NSE77-A27023
High-Resolution Gamma-Ray Spectrum from Concrete
S. K. Gupta
Nuclear Science and Engineering | Volume 63 | Number 2 | June 1977 | Pages 193-197
Technical Note | doi.org/10.13182/NSE77-A27024
Cross Section for the Production of Beryllium-7 from Lithium-6, Lithium-6 Interactions
Lawrence Ruby, Robert V. Pyle, Yue-Chau Wong
Nuclear Science and Engineering | Volume 63 | Number 2 | June 1977 | Pages 197-198
Technical Note | doi.org/10.13182/NSE77-A27025
Fission Cross Section of Berkelium-249 Between 0.7 and 3.0 MeV
M. G. Silbert
Nuclear Science and Engineering | Volume 63 | Number 2 | June 1977 | Pages 198-200
Technical Note | doi.org/10.13182/NSE77-A27026
Hydrogen and Helium Production Cross Sections for 15-MeV Neutrons on Types 316 and 304 Stainless Steel
R. C. Haight, S. M. Grimes, J. D. Anderson
Nuclear Science and Engineering | Volume 63 | Number 2 | June 1977 | Pages 200-204
Technical Note | doi.org/10.13182/NSE77-A27027
Accurate Approximations to Average Beta-Particle Energies and Spectra
M. G. Stamatelatos, T. R. England
Nuclear Science and Engineering | Volume 63 | Number 2 | June 1977 | Pages 204-208
Technical Note | doi.org/10.13182/NSE77-A27028
Monte Carlo Calculations of Cadmium Cutoff Energies and an Ansatz Formula
S. Fiarman, R. Sher
Nuclear Science and Engineering | Volume 63 | Number 2 | June 1977 | Pages 208-212
Technical Note | doi.org/10.13182/NSE77-A27029
Wigner-Type Continuous Slowing Down Theory for the Fast-Neutron Spectrum
Yasunori Yamamura, Tamotsu Sekiya
Nuclear Science and Engineering | Volume 63 | Number 2 | June 1977 | Pages 213-217
Technical Note | doi.org/10.13182/NSE77-A27030
Discrete Neutron Decay Constants Above the Corngold Limit for Infinite Slabs
N. G. Sjöstrand
Nuclear Science and Engineering | Volume 63 | Number 2 | June 1977 | Pages 217-218
Technical Note | doi.org/10.13182/NSE77-A27031
A Comparison of Constrained Finite Elements and Response Matrices as One-Dimensional Transport Approximations
L. L. Briggs, E. E. Lewis
Nuclear Science and Engineering | Volume 63 | Number 3 | July 1977 | Pages 225-235
Technical Paper | doi.org/10.13182/NSE77-A27035
Elastic Neutron Scattering from Distributed Fusion Neutrons, Deuterium, Tritium, and Lithium, and Multigroup Rate Coefficients
B. R. Wienke, R. E. Seamon
Nuclear Science and Engineering | Volume 63 | Number 3 | July 1977 | Pages 236-241
Technical Paper | doi.org/10.13182/NSE77-A27036
Calculated Neutron Capture Cross Sections to the Americium Ground and Isomeric States
F. M. Mann, R. E. Schenter
Nuclear Science and Engineering | Volume 63 | Number 3 | July 1977 | Pages 242-249
Technical Paper | doi.org/10.13182/NSE77-A27037
Measurements of the Neutron-Induced Fission Cross Sections of 234U, 236U, and 238U Relative to 235U from 0.1 to 30 MeV
J. W. Behrens, G. W. Carlson
Nuclear Science and Engineering | Volume 63 | Number 3 | July 1977 | Pages 250-267
Technical Paper | doi.org/10.13182/NSE77-2
Measurement of the 58Ni(n, p)58Co Cross Section with H(n, n)p as a Standard
Mien-Win Wu, Jen-Chang Chou
Nuclear Science and Engineering | Volume 63 | Number 3 | July 1977 | Pages 268-275
Technical Paper | doi.org/10.13182/NSE77-A27039
Uncertainties in Fission Product Decay-Heat Calculations
F. Schmittroth, R. E. Schenter
Nuclear Science and Engineering | Volume 63 | Number 3 | July 1977 | Pages 276-291
Technical Paper | doi.org/10.13182/NSE77-A27040
Thermal-Neutron Behavior in Cluster-Type Plutonium Fuel Lattices
T. Wakabayashi, Y. Hachiya
Nuclear Science and Engineering | Volume 63 | Number 3 | July 1977 | Pages 292-305
Technical Paper | doi.org/10.13182/NSE77-A27041
Theoretical Investigation of the Local and Global Components of the Neutron-Noise Field in a Boiling Water Reactor
K. Behringer, G. Kosály, Lj. Kostić
Nuclear Science and Engineering | Volume 63 | Number 3 | July 1977 | Pages 306-318
Technical Paper | doi.org/10.13182/NSE77-A27042
Effects of Fast-Neutron Irradiation and High-Intensity Magnetic Fields upon Cavitation Thresholds and Nuclei Spectra in Water
E. Yilmaz, F. G. Hammitt
Nuclear Science and Engineering | Volume 63 | Number 3 | July 1977 | Pages 319-329
Technical Paper | doi.org/10.13182/NSE77-A27043
Determination of the Probing Distance in Pulsed-Neutron Uranium Logging Experiments
James H. Renken
Nuclear Science and Engineering | Volume 63 | Number 3 | July 1977 | Pages 330-335
Technical Paper | doi.org/10.13182/NSE77-A27044
A Parametric Analysis of the Spallation Breeder
A. A. Harms, C. W. Gordon
Nuclear Science and Engineering | Volume 63 | Number 3 | July 1977 | Pages 336-341
Technical Note | doi.org/10.13182/NSE77-A27045
The Tritium Production in a Controlled Thermonuclear Reactor Blanket Model with a Graphite Reflector
R. Herzing, L. Kuijpers, P. Cloth, D. Filges, R. Hecker, N. Kirch
Nuclear Science and Engineering | Volume 63 | Number 3 | July 1977 | Pages 341-343
Technical Note | doi.org/10.13182/NSE77-A27046
Thermonuclear Reaction Rate Parameters for d + 6Li Reactions
A. J. Elwyn, J. E. Monahan, F. J. D. Serduke
Nuclear Science and Engineering | Volume 63 | Number 3 | July 1977 | Pages 343-346
Technical Note | doi.org/10.13182/NSE77-A27047
A Perturbation Analysis of Changes in Prompt Fission Neutron Uranium-Logging Signals Produced by Trace Neutron-Absorbing Rock Constituents
Nuclear Science and Engineering | Volume 63 | Number 3 | July 1977 | Pages 347-349
Technical Note | doi.org/10.13182/NSE77-A27048
Solidification of a Sphere with Internal Heat Generation and Convective Cooling at the Surface
Vijay K. Dhir, Kin Wong, W. E. Kastenberg
Nuclear Science and Engineering | Volume 63 | Number 3 | July 1977 | Pages 350-356
Technical Note | doi.org/10.13182/NSE77-A27049
Nonequilibrium Critical Discharge of Saturated and Subcooled Liquid Freon-11
Michael R. Prisco, Robert E. Henry, Michael N. Hutcherson, John L. Linehan
Nuclear Science and Engineering | Volume 63 | Number 4 | August 1977 | Pages 365-375
Technical Paper | doi.org/10.13182/NSE77-A27054
Estimation of Nuclear Decay Heat for Short-Lived Fission Products
Tadashi Yoshida
Nuclear Science and Engineering | Volume 63 | Number 4 | August 1977 | Pages 376-390
Technical Paper | doi.org/10.13182/NSE77-A27055
Neutron Thermalization Spectrum in a Partially Hydrogenated Terphenyl: Evaluation of Scattering Kernels for Organic Reactor Coolant
H. Alan Robitaille, John S. Hewitt
Nuclear Science and Engineering | Volume 63 | Number 4 | August 1977 | Pages 391-400
Technical Paper | doi.org/10.13182/NSE77-A27056
Double-Differential Beryllium Neutron Cross Sections at Incident Neutron Energies of 5.9, 10.1, and 14.2 MeV
D. M. Drake, G. F. Auchampaugh, E. D. Arthur, C. E. Ragan, P. G. Young
Nuclear Science and Engineering | Volume 63 | Number 4 | August 1977 | Pages 401-412
Technical Paper | doi.org/10.13182/NSE77-A27057
Thermal-Neutron Capture and Fission Cross Sections and Resonance Integrals for Curium-243
C. E. Bemis, Jr., J. H. Oliver, R. Eby, J. Halperin
Nuclear Science and Engineering | Volume 63 | Number 4 | August 1977 | Pages 413-417
Technical Paper | doi.org/10.13182/NSE77-A27058
High-Resolution Fast-Neutron Gamma-Ray Production Cross Sections for Iron up to 2100 keV
W. E. Kinney, F. G. Perey
Nuclear Science and Engineering | Volume 63 | Number 4 | August 1977 | Pages 418-429
Technical Paper | doi.org/10.13182/NSE77-A27059
A Reconciliation of Measurements of for Neutron-Induced Fission of Uranium-235
J. W. Boldeman, J. Fréhaut, R. L. Walsh
Nuclear Science and Engineering | Volume 63 | Number 4 | August 1977 | Pages 430-436
Technical Paper | doi.org/10.13182/NSE77-A27060
Coarse-Mesh Flux-Expansion Method for the Analysis of Space-Time Effects in Large Light Water Reactor Cores
S. Langenbuch, W. Maurer, W. Werner
Nuclear Science and Engineering | Volume 63 | Number 4 | August 1977 | Pages 437-456
Technical Paper | doi.org/10.13182/NSE77-A27061
Some Basic Properties of the Response Matrix Equations
Zbigniew Weiss
Nuclear Science and Engineering | Volume 63 | Number 4 | August 1977 | Pages 457-492
Technical Paper | doi.org/10.13182/NSE77-A27062
Measurements of Energy Spectra and Doses in Liquid Air of Neutrons from a Californium-252 Source
K. Clausen, U. Roose, P. Schneider-Kühnle, F. W. Buchholz, L. Schänzler, S. Stüker, G. Tumbrägel, M. Weinert
Nuclear Science and Engineering | Volume 63 | Number 4 | August 1977 | Pages 493-500
Technical Note | doi.org/10.13182/NSE77-A27063
Space- and Angle-Dependent Steady-State Thermal-Neutron Spectra Inside Small Beryllium Assemblies: II
Suresh Garg, Feroz Ahmed, L. S. Kothari
Nuclear Science and Engineering | Volume 63 | Number 4 | August 1977 | Pages 500-504
Technical Note | doi.org/10.13182/NSE77-A27064
Distribution of Fission Yields for Fission Spectrum Neutron-Induced Fission of Uranium-238
D. C. Harris, J. N. Beck, W. L. Raines, J. T. Harvey, K. G. W. Inn, J. L. Meason, H. L. Wright
Nuclear Science and Engineering | Volume 63 | Number 4 | August 1977 | Pages 504-507
Technical Note | doi.org/10.13182/NSE77-A27065
Two-Half-Space Milne Problem in Two-Group Neutron Transport Theory
Yuji Ishiguro, José Rubens Maiorino
Nuclear Science and Engineering | Volume 63 | Number 4 | August 1977 | Pages 507-509
Technical Note | doi.org/10.13182/NSE77-A27066
Upper-Bound Estimation of Bilinear Functionals in Reactor Theory
Yigal Ronen, Ehud Greenspan
Nuclear Science and Engineering | Volume 63 | Number 4 | August 1977 | Pages 509-513
Technical Note | doi.org/10.13182/NSE77-A27067
