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Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
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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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A Multivariable Autoregressive Model of the Dynamics of a Boiling Water Reactor
K. Matsubara, R. Oguma, M. Kitamura
Nuclear Science and Engineering | Volume 65 | Number 1 | January 1978 | Pages 1-16
Technical Paper | doi.org/10.13182/NSE78-A27121
Void Distribution in Boiling Pools with Internal Heat Generation
Mujid S. Kazimi, John C. Chen
Nuclear Science and Engineering | Volume 65 | Number 1 | January 1978 | Pages 17-27
Technical Paper | doi.org/10.13182/NSE78-A27122
Pinhole Imaging of a Test Fuel Element at the Transient Reactor Test Facility
George J. Berzins, Ki S. Han
Nuclear Science and Engineering | Volume 65 | Number 1 | January 1978 | Pages 28-40
Technical Paper | doi.org/10.13182/NSE78-A27123
Critical Experiments Measuring the Reactivity Worths of Materials Commonly Encountered as Fixed Neutron Absorbers
S. R. Bierman, B. M. Durst, E. D. Clayton
Nuclear Science and Engineering | Volume 65 | Number 1 | January 1978 | Pages 41-48
Technical Paper | doi.org/10.13182/NSE78-A27124
Cross Sections for Gamma-Ray Production by 1A-MeV Neutrons
D. M. Drake, E. D. Arthur, M. G. Silbert
Nuclear Science and Engineering | Volume 65 | Number 1 | January 1978 | Pages 49-64
Technical Paper | doi.org/10.13182/NSE78-A27125
Differential Elastic Scattering Cross Sections of Boron-10 for Neutrons of 4 to 8 MeV Energy
H. D. Knox, R. M. White, R. O. Lane
Nuclear Science and Engineering | Volume 65 | Number 1 | January 1978 | Pages 65-69
Technical Paper | doi.org/10.13182/NSE78-A27126
The Differential Neutron Scattering Cross Sections of Uranium-238 at 144 keV
Francis Y. Tsang, Robert M. Brugger
Nuclear Science and Engineering | Volume 65 | Number 1 | January 1978 | Pages 70-75
Technical Paper | doi.org/10.13182/NSE78-A27127
Neutron Resonance Spectroscopy in Vanadium, Manganese, and Cobalt
J. B. Garg
Nuclear Science and Engineering | Volume 65 | Number 1 | January 1978 | Pages 76-92
Technical Paper | doi.org/10.13182/NSE78-A27128
A New Monte Carlo Approach to the Adjoint Boltzmann Equation
Artenio De Matteis, Rolando Simonini
Nuclear Science and Engineering | Volume 65 | Number 1 | January 1978 | Pages 93-105
Technical Paper | doi.org/10.13182/NSE78-A27129
Space-Time Dynamics of a Fast Breeder Reactor for Localized Disturbances
Jagdeep B. Doshi, Lawrence M. Grossman
Nuclear Science and Engineering | Volume 65 | Number 1 | January 1978 | Pages 106-129
Technical Paper | doi.org/10.13182/NSE78-A27130
A Computational Method for Neutron Transport Problems in Toroidal Geometry
Jungchung Jung
Nuclear Science and Engineering | Volume 65 | Number 1 | January 1978 | Pages 130-140
Technical Paper | doi.org/10.13182/NSE78-A27131
Radiation Behavior of Vitreous Silica
William Primak
Nuclear Science and Engineering | Volume 65 | Number 1 | January 1978 | Pages 141-145
Technical Note | doi.org/10.13182/NSE78-A27132
Two-Dimensional Void Reconstruction by Neutron Transmission
G. D. Zakaib, A. A. Harms, J. Vlachopoulos
Nuclear Science and Engineering | Volume 65 | Number 1 | January 1978 | Pages 145-154
Technical Note | doi.org/10.13182/NSE78-A27133
Experimental Investigation of Neutrons Streaming Through the Grid-Plate Shield of Liquid-Metal Fast Breeder Reactors
Shunsuke Uchida, Masao Kitamura, Shunichi Miyasaka
Nuclear Science and Engineering | Volume 65 | Number 1 | January 1978 | Pages 155-159
Technical Note | doi.org/10.13182/NSE78-A27134
Measurement of the Neutron Spectrum from a Fast Pulse Reactor in the Presence of the Experimenter's Table
J. T. Harvey, J. L. Meason, H. L. Wright
Nuclear Science and Engineering | Volume 65 | Number 1 | January 1978 | Pages 160-161
Technical Note | doi.org/10.13182/NSE78-A27135
On the Spherical Harmonics Treatment of Epithermal-Neutron Spectra in Reactor Lattices—Further Developments and Improvements
M. V. Mataušek
Nuclear Science and Engineering | Volume 65 | Number 1 | January 1978 | Pages 161-164
Technical Note | doi.org/10.13182/NSE78-A27136
Fast-Neutron Cross Sections for Curium-244
Horacio Fernández Gianotti
Nuclear Science and Engineering | Volume 65 | Number 1 | January 1978 | Pages 164-166
Technical Note | doi.org/10.13182/NSE78-A27137
Fission Cross Section for Curium-245 from 0.01 to 35 eV
J. C. Browne, R. W. Benjamin, D. G. Karraker
Nuclear Science and Engineering | Volume 65 | Number 1 | January 1978 | Pages 166-170
Technical Note | doi.org/10.13182/NSE78-A27138
The Fission Cross Sections of Uranium-234 and Uranium-236 Relative to Uranium-235
J. W. Meadows
Nuclear Science and Engineering | Volume 65 | Number 1 | January 1978 | Pages 171-174
Technical Note | doi.org/10.13182/NSE78-2
Neutron Scattering and the Optical Model near A = 208 and Implications on the Inelastic Scattering Cross Section of Uranium-238
P. T. Guenther, D. G. Havel, A. B. Smith
Nuclear Science and Engineering | Volume 65 | Number 1 | January 1978 | Pages 174-180
Technical Note | doi.org/10.13182/NSE78-A27140
Neutron Diffusion Across an Absorption Discontinuity in Water Assemblies
S. K. Trikha, S. C. Jain
Nuclear Science and Engineering | Volume 65 | Number 1 | January 1978 | Pages 180-182
Technical Note | doi.org/10.13182/NSE78-A27141
Tailoring the Breeding-Fission Ratio in a Hybrid Fusion Reactor Blanket by Neutron Moderation with Iron
Gad Shani
Nuclear Science and Engineering | Volume 65 | Number 1 | January 1978 | Pages 183-187
Technical Note | doi.org/10.13182/NSE78-A27142
Sensitivity Theory for General Nonlinear Algebraic Equations with Constraints
E. M. Oblow
Nuclear Science and Engineering | Volume 65 | Number 1 | January 1978 | Pages 187-191
Technical Note | doi.org/10.13182/NSE78-A27143
On Multiregion Problems in Plane Geometry and the Use of Half-Range Orthogonality Relations
Yuji Ishiguro
Nuclear Science and Engineering | Volume 65 | Number 1 | January 1978 | Pages 191-196
Technical Note | doi.org/10.13182/NSE78-A27144
The CN Method of Solving the Transport Equation: Application to Plane Geometry
Alain Kavenoky
Nuclear Science and Engineering | Volume 65 | Number 2 | February 1978 | Pages 209-225
Technical Paper | doi.org/10.13182/NSE78-A27152
Generalized Rebalance: A Common Framework for Transport Acceleration Methods
W. F. Miller, Jr.
Nuclear Science and Engineering | Volume 65 | Number 2 | February 1978 | Pages 226-236
Technical Paper | doi.org/10.13182/NSE78-A27153
Application of the Fictitious Scattering Radiation Transport Model for Deep-Penetration Monte Carlo Calculations
S. N. Cramer
Nuclear Science and Engineering | Volume 65 | Number 2 | February 1978 | Pages 237-253
Technical Paper | doi.org/10.13182/NSE78-A27154
Multidimensional Space-Time Nuclear Reactor Kinetics Studies. Part III: Three-Dimensional Experiments
W. G. Winn, P. B. Parks, N. P. Baumann, C. E. Jewell
Nuclear Science and Engineering | Volume 65 | Number 2 | February 1978 | Pages 254-272
Technical Paper | doi.org/10.13182/NSE78-A27155
Prediction of Monte Carlo Errors by a Theory Generalized to Treat Track-Length Estimators
Thomas E. Booth, Harvey J. Amster
Nuclear Science and Engineering | Volume 65 | Number 2 | February 1978 | Pages 273-281
Technical Paper | doi.org/10.13182/NSE78-A27156
Critical Impurity Concentrations for Power Multiplication in Beam-Heated Toroidal Fusion Reactors
R. V. Jensen, D. E. Post, D. L. Jassby
Nuclear Science and Engineering | Volume 65 | Number 2 | February 1978 | Pages 282-289
Technical Paper | doi.org/10.13182/NSE78-A27157
Neutron Drift in Heterogeneous Media
Edward W. Larsen, Michael Williams
Nuclear Science and Engineering | Volume 65 | Number 2 | February 1978 | Pages 290-302
Technical Paper | doi.org/10.13182/NSE78-A27158
Calculation of Neutron and Gamma-Ray Energy Spectra in Liquid Air and Liquid Nitrogen Due to 14-MeV Neutron and Californium-252 Sources
E. A. Straker, M. L. Gritzner, L. Harris, Jr.
Nuclear Science and Engineering | Volume 65 | Number 2 | February 1978 | Pages 303-315
Technical Paper | doi.org/10.13182/NSE78-A27159
Threshold-Foil Measurements of Reactor Neutron Spectra for Radiation Damage Applications
Victor V. Verbinski, Norman A. Lurie, Vern C. Rogers
Nuclear Science and Engineering | Volume 65 | Number 2 | February 1978 | Pages 316-330
Technical Paper | doi.org/10.13182/NSE78-A27160
Measurement of the Differential Elastic and Inelastic Neutron Scattering Cross Sections of Carbon from 8.0 to 14.5 MeV
G. Haouat, J. Lachkar, J. Sigaud, Y. Patin, F. Coçu
Nuclear Science and Engineering | Volume 65 | Number 2 | February 1978 | Pages 331-346
Technical Paper | doi.org/10.13182/NSE78-A27161
Neutron Total Cross-Section Measurement of Thorium Near 24 keV with an Iron-Filtered Neutron Beam
Katsuhei Kobayashi, Yoshiaki Fujita, Tohru Oosaki, Robert C. Block
Nuclear Science and Engineering | Volume 65 | Number 2 | February 1978 | Pages 347-353
Technical Paper | doi.org/10.13182/NSE78-A27162
Use of Interactive Graphic Techniques to Evaluate Uranium-238 Cross Sections from Integral Measurements
Ansar Parvez, Martin Becker
Nuclear Science and Engineering | Volume 65 | Number 2 | February 1978 | Pages 354-367
Technical Paper | doi.org/10.13182/NSE78-A27163
Application of Nuclear Reaction Models for Neutron Nuclear Data Evaluation: Statistical and Optical Model Calculations for 134–138Ba
B. Strohmaier, M. Uhl, W. K. Matthes
Nuclear Science and Engineering | Volume 65 | Number 2 | February 1978 | Pages 368-384
Technical Paper | doi.org/10.13182/NSE78-A27164
A Digital Transfer Matrix for Fuel Pin Heat Transfer
Michael D. Green, Jak Kornfilt
Nuclear Science and Engineering | Volume 65 | Number 2 | February 1978 | Pages 385-393
Technical Paper | doi.org/10.13182/NSE78-A27165
Experimental Studies of the Growth of an Internally Heated Liquid Pool in a Solid Bed
Rouyentan Farhadieh, Louis Baker, Jr.
Nuclear Science and Engineering | Volume 65 | Number 2 | February 1978 | Pages 394-400
Technical Paper | doi.org/10.13182/NSE78-A27166
Probabilistic Analysis of Liquid-Metal Fast Breeder Reactor Accident Consequences with Response Surface Techniques
J. K. Vaurio, C. Mueller
Nuclear Science and Engineering | Volume 65 | Number 2 | February 1978 | Pages 401-413
Technical Paper | doi.org/10.13182/NSE78-A27167
Approximation to cosγ Appearing in the Formula for the Coulomb Scattering of Relativistic Electrons
Tatsuo Tabata, Rinsuke Ito
Nuclear Science and Engineering | Volume 65 | Number 2 | February 1978 | Pages 414-415
Technical Note | doi.org/10.13182/NSE78-A27168
Restrained Acceleration in Iteration
D. R. Vondy, T. B. Fowler
Nuclear Science and Engineering | Volume 65 | Number 2 | February 1978 | Pages 415-416
Technical Note | doi.org/10.13182/NSE78-A27169
Some Observations on Transverse Leakage Approximations in Multidimensional Transport Theory
M. M. R. Williams, J. M. Kallfelz
Nuclear Science and Engineering | Volume 65 | Number 2 | February 1978 | Pages 416-419
Technical Note | doi.org/10.13182/NSE78-A27170
The Effect of Non-1/v Absorbers on Thermal-Neutron Transport in Finite Size Assemblies of Water and Heavy Water
R. M. Bansal, S. P. Tewari
Nuclear Science and Engineering | Volume 65 | Number 2 | February 1978 | Pages 419-422
Technical Note | doi.org/10.13182/NSE78-A27171
Thermal Expansion Worths for a Liquid-Metal Fast Breeder Reactor Inferred from Small-Sample Reactivity Measurements
B. Wei-Teh Lee, R. E. Kaiser, J. T. Hitchcock, C. S. Russell
Nuclear Science and Engineering | Volume 65 | Number 3 | March 1978 | Pages 429-440
Technical Paper | doi.org/10.13182/NSE78-A27174
An Evaluation of ENDF/B-IV and Hansen-Roach Uranium-233 Cross Sections for Use in Criticality Calculations
S. R. McNeany, J. D. Jenkins
Nuclear Science and Engineering | Volume 65 | Number 3 | March 1978 | Pages 441-453
Technical Paper | doi.org/10.13182/NSE78-A27175
Neutron Capture and Fission Cross Sections of Plutonium-241
L. W. Weston, J. H. Todd
Nuclear Science and Engineering | Volume 65 | Number 3 | March 1978 | Pages 454-463
Technical Paper | doi.org/10.13182/NSE78-A27176
Predictions of Fission Cross Sections in the 3- to 5-MeV Neutron Energy Range
J. W. Behrens, R. J. Howerton
Nuclear Science and Engineering | Volume 65 | Number 3 | March 1978 | Pages 464-467
Technical Paper | doi.org/10.13182/NSE65-464
Practical Formalisms for Nuclear Data Representation in Evaluated Nuclear Data Files in the Unresolved Resonance Energy Region
Y. Gur, S. Yiftah
Nuclear Science and Engineering | Volume 65 | Number 3 | March 1978 | Pages 468-476
Technical Paper | doi.org/10.13182/NSE78-A27178
Consistent Utilization of Shielding Benchmark Experiments
A. D'Angelo, A. Oliva, G. Palmiotti, M. Salvatores, S. Zero
Nuclear Science and Engineering | Volume 65 | Number 3 | March 1978 | Pages 477-491
Technical Paper | doi.org/10.13182/NSE78-A27179
Substitution Measurements on 28-Fuel-Rod Critical Clusters in D2O and Their Analysis by the Second-Order Perturbation Method
Kiminori Shiba
Nuclear Science and Engineering | Volume 65 | Number 3 | March 1978 | Pages 492-507
Technical Paper | doi.org/10.13182/NSE78-A27180
A Linear Stability Analysis of Reactors with a Delayed Temperature Feedback
Trine-Yie Dawn, Chio-Min Yang
Nuclear Science and Engineering | Volume 65 | Number 3 | March 1978 | Pages 508-513
Technical Paper | doi.org/10.13182/NSE78-A27181
The CN Method of Solving the Transport Equation: Application to Cylindrical Geometry
Nuclear Science and Engineering | Volume 65 | Number 3 | March 1978 | Pages 514-531
Technical Paper | doi.org/10.13182/NSE78-A27182
Iterative Solution of the Neutron Transport Equation by Means of Diffusion Techniques
M. Michelini
Nuclear Science and Engineering | Volume 65 | Number 3 | March 1978 | Pages 532-539
Technical Paper | doi.org/10.13182/NSE78-A27183
Neutron Heating Sensitivity to Cross-Section Variations in a Controlled Thermonuclear Reactor Blanket
B. Arcipiani, G. Palmiotti, M. Salvatores
Nuclear Science and Engineering | Volume 65 | Number 3 | March 1978 | Pages 540-544
Technical Note | doi.org/10.13182/NSE78-A27184
Production of Uranium-232 in a 1200-MW(e) Liquid-Metal Fast Breeder Reactor
F. M. Mann, R. E. Schenter
Nuclear Science and Engineering | Volume 65 | Number 3 | March 1978 | Pages 544-547
Technical Note | doi.org/10.13182/NSE78-A27185
Measurement of the Uranium-238 Doppler Effect in Gas-Cooled Fast Reactor Critical Assemblies
S. K. Bhattacharyya, R. B. Pond
Nuclear Science and Engineering | Volume 65 | Number 3 | March 1978 | Pages 548-553
Technical Note | doi.org/10.13182/NSE78-A27186
On the Energy Dependence of the Total Cross Section of the Reaction 2H(d, n)3He
M. Drosg
Nuclear Science and Engineering | Volume 65 | Number 3 | March 1978 | Pages 553-554
Technical Note | doi.org/10.13182/NSE78-A27187
A First-Order Approximation to Fast-Neutron Penetration Spectra for Non-Normally Incident Neutrons on Water Slabs
William H. Miller, David Hollabaugh, Walter Meyer
Nuclear Science and Engineering | Volume 65 | Number 3 | March 1978 | Pages 554-557
Technical Note | doi.org/10.13182/NSE78-A27188
Effects of Isotopic Abundance on Kerma in Naturally Occurring Targets: Chlorine
Martin S. Spergel, Otto W. Lazareth
Nuclear Science and Engineering | Volume 65 | Number 3 | March 1978 | Pages 558-560
Technical Note | doi.org/10.13182/NSE78-A27189
Expansion About a Local Maxwellian for Evaluating the Spatially Dependent Neutron Spectrum
V. G. Molinari, R. Simonini
Nuclear Science and Engineering | Volume 65 | Number 3 | March 1978 | Pages 560-565
Technical Note | doi.org/10.13182/NSE78-A27190
Kinetic Parameters of the University of Maryland Reactor by the Interval-Distribution Method
John A. Rawlins, S. Christian Simonson III
Nuclear Science and Engineering | Volume 65 | Number 3 | March 1978 | Pages 565-567
Technical Note | doi.org/10.13182/NSE78-A27191