Nuclear Science and Engineering -- ANS / Publications / Journals / Nuclear Science and Engineering

About ANS
- ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
About Nuclear
- Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Communities
- Division Spotlight
  Young Members Group
  The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
Events
- Meeting Spotlight
  Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
  February 3–6, 2025
  Amelia Island, FL|Omni Amelia Island Resort
Standards
- Standards Program
  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!
Publications
- Latest Magazine Issues
  Jan 2025
  Jul 2024
  Latest Journal Issues
  Nuclear Science and Engineering
  February 2025
  Nuclear Technology
  January 2025
  Fusion Science and Technology
  February 2025
- Latest News
  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.
Search

Jump to:

Number 1
Number 2

Number 3
Number 4

Number 1

Table of Contents
Experimental Reactor Physics (Glenn F. Knoll)
Fusion Energy Conversion (J. Rand McNally, Jr.)
Safeguards Against Nuclear Proliferation (Melvin L. Tobias)
Transport Eigenvalues (Jeffery Lewins)
The Reactivity Dependence of Neutron Energy Spectra (Y. Ronen, D. Shalitin, D. Shvarts, J. J. Wags chat, Y. Yeivìn)

Reactivity and Power Shape Control
Constantine P. Tzanos
Nuclear Science and Engineering | Volume 62 | Number 1 | January 1977 | Pages 1-8
Technical Paper | doi.org/10.13182/NSE77-A26934
Suboptimal Control of Nuclear Reactors with Distributed Parameters Using Singular Perturbation Theory
K. Asatani, M. Shiotani, Y. Hattori
Nuclear Science and Engineering | Volume 62 | Number 1 | January 1977 | Pages 9-19
Technical Paper | doi.org/10.13182/NSE77-A26935
Fault Trees for Diagnosis of System Fault Conditions
Howard E. Lambert, George Yadigaroglu
Nuclear Science and Engineering | Volume 62 | Number 1 | January 1977 | Pages 20-34
Technical Paper | doi.org/10.13182/NSE77-A26936
The Sensitivity of Decay Power to Uncertainties in Fission Product Yields
B. I. Spinrad
Nuclear Science and Engineering | Volume 62 | Number 1 | January 1977 | Pages 35-44
Technical Paper | doi.org/10.13182/NSE77-A26937
An Approximate Calculational Method for Nuclear Heating
Gene L. Woodruff, David C. Quimby
Nuclear Science and Engineering | Volume 62 | Number 1 | January 1977 | Pages 45-54
Technical Paper | doi.org/10.13182/NSE77-A26938
Singularities in the Finite Element Approximation of Two-Dimensional Diffusion Problems
J. P. Hennart, E. H. Mund
Nuclear Science and Engineering | Volume 62 | Number 1 | January 1977 | Pages 55-68
Technical Paper | doi.org/10.13182/NSE77-A26939
Improved Formulations of the Response Matrix Doubling Equations
W. L. Filippone
Nuclear Science and Engineering | Volume 62 | Number 1 | January 1977 | Pages 69-91
Technical Paper | doi.org/10.13182/NSE77-A26940
The Concept of Spatial Channel Theory Applied to Reactor Shielding Analysis
M. L. Williams, W. W. Engle, Jr.
Nuclear Science and Engineering | Volume 62 | Number 1 | January 1977 | Pages 92-104
Technical Paper | doi.org/10.13182/NSE77-A26941
Integral Measurements of the Effective Delayed Neutron Fractions in the Fast Critical Assembly SNEAK
E. A. Fischer
Nuclear Science and Engineering | Volume 62 | Number 1 | January 1977 | Pages 105-116
Technical Paper | doi.org/10.13182/NSE77-4
Methods of Adjustment and Error Evaluation of Neutron Capture Cross Sections; Application to Fission Product Nuclides
J. B. Dragt, J. W. M. Dekker, H. Gruppelaar, A. J. Janssen
Nuclear Science and Engineering | Volume 62 | Number 1 | January 1977 | Pages 117-129
Technical Paper | doi.org/10.13182/NSE77-3
Source Enhancement Measurement to Determine vσ_ƒ of Uranium-238 for Californium-252 Spontaneous Fission Neutrons
B. W. Lee, S. H. Levine
Nuclear Science and Engineering | Volume 62 | Number 1 | January 1977 | Pages 130-136
Technical Paper | doi.org/10.13182/NSE77-A26944
Cross-Section Sensitivity and Uncertainty Analysis with Application to a Fusion Reactor
S. A. W. Gerstl, Donald J. Dudziak, D. W. Muir
Nuclear Science and Engineering | Volume 62 | Number 1 | January 1977 | Pages 137-156
Technical Paper | doi.org/10.13182/NSE77-A26945
Grain Boundary Grooving of Pure Iron in Nitrogen-Contaminated Liquid Lithium
L. B. Whitefield, D. L. Olson, W. L. Bradley
Nuclear Science and Engineering | Volume 62 | Number 1 | January 1977 | Pages 157-162
Technical Paper | doi.org/10.13182/NSE77-A26946
Dimensionality Reduction of Reactor Noise Signatures
R. C. Gonzalez, L. C. Howington
Nuclear Science and Engineering | Volume 62 | Number 1 | January 1977 | Pages 163-167
Technical Note | doi.org/10.13182/NSE77-A26947
Effects of Neutron Capture Transformations on the Decay Power of Fission Products
Kanji Tasaka
Nuclear Science and Engineering | Volume 62 | Number 1 | January 1977 | Pages 167-174
Technical Note | doi.org/10.13182/NSE77-A26948
The 292.4-eV Neutron Resonance Parameters of Zirconium-91
R. L. Macklin, J. A. Harvey, J. Halperin, N. W. Hill
Nuclear Science and Engineering | Volume 62 | Number 1 | January 1977 | Pages 174-176
Technical Note | doi.org/10.13182/NSE77-A26949

Number 2

Table of Contents
Experimental Development of Design Criteria to Limit Liquid Cross-Flow-Induced Vibration in Nuclear Reactor Heat Exchange Equipment (D. J. Gorman)
Nuclear Reactor Analysis (Noel Corngold)
Annual Review of Energy, Volume 1 (H. G. MacPherson)
The Nuclear Fuel Cycle—A Survey of the Public Health, Environmental, and National Security Effects of Nuclear Power (Melvin L. Tobias)
Stress Transients in Solids (J. E. Akin)

Measurement of Sub-Coulomb-Barrier Charged Particles Emitted from Aluminum and Titanium Bombarded by 15-MeV Neutrons
S. M. Grimes, R. C. Haight, J. D. Anderson
Nuclear Science and Engineering | Volume 62 | Number 2 | February 1977 | Pages 187-194
Technical Paper | doi.org/10.13182/NSE77-A26956
FX2-POOL—A Two-Dimensional Coupled Hydrodynamic Thermodynamic and Neutronic Computer Model for Hypothetical Core Disruptive Accident Analysis
Paul B. Abramson
Nuclear Science and Engineering | Volume 62 | Number 2 | February 1977 | Pages 195-214
Technical Paper | doi.org/10.13182/NSE77-A26957
Diagnostic Analyses of a Nuclear Power Plant Using Multivariate Autoregressive Processes
Kohyu Fukunishi
Nuclear Science and Engineering | Volume 62 | Number 2 | February 1977 | Pages 215-225
Technical Paper | doi.org/10.13182/NSE77-A26958
The Effect of Core Burnup on the Dynamic Behavior of Fast Reactors
D. Ilberg, D. Saphier, S. Yiftah
Nuclear Science and Engineering | Volume 62 | Number 2 | February 1977 | Pages 226-242
Technical Paper | doi.org/10.13182/NSE77-A26959
Derivation of Consistent Measures for the Doubling of Fast Breeder Reactor Fuel
Karl O. Ott, Robert C. Borg
Nuclear Science and Engineering | Volume 62 | Number 2 | February 1977 | Pages 243-261
Technical Paper | doi.org/10.13182/NSE77-A26960
Measured Fast-Neutron Penetration Spectra for Water—Comparison with Calculations
William H. Miller, Walter Meyer, Darrol H. Timmons
Nuclear Science and Engineering | Volume 62 | Number 2 | February 1977 | Pages 262-269
Technical Paper | doi.org/10.13182/NSE77-A26961
The Representation of Water Properties by Mathematical Splines
C. S. Caldwell, D. A. Spragg
Nuclear Science and Engineering | Volume 62 | Number 2 | February 1977 | Pages 270-277
Technical Paper | doi.org/10.13182/NSE77-A26962
Orders-of-Scattering Analysis of Particle Transport in Finite Slabs
Stanley Woolf, John C. Garth, William L. Filippone
Nuclear Science and Engineering | Volume 62 | Number 2 | February 1977 | Pages 278-295
Technical Paper | doi.org/10.13182/NSE77-A26963
Perturbation Theory for Ratios in Linear and Nonlinear Problems
Martin Becker
Nuclear Science and Engineering | Volume 62 | Number 2 | February 1977 | Pages 296-301
Technical Paper | doi.org/10.13182/NSE77-A26964
Estimation of Specific Heat of Superheated Water
John H. Lienhard
Nuclear Science and Engineering | Volume 62 | Number 2 | February 1977 | Pages 302-304
Technical Note | doi.org/10.13182/NSE77-A26965
Burnup Calculations with Time-Dependent Generalized Perturbation Theory
J. M. Kallfelz, G. B. Bruna, G. Palmiotti, M. Salvatores
Nuclear Science and Engineering | Volume 62 | Number 2 | February 1977 | Pages 304-309
Technical Note | doi.org/10.13182/NSE77-A26966
Benchmark Testing Using ENDF/B-III and -IV
R. D. McKnight
Nuclear Science and Engineering | Volume 62 | Number 2 | February 1977 | Pages 309-330
Technical Note | doi.org/10.13182/NSE77-A26967
An Improved P-L Solution to the Reflected Critical-Reactor Problem in Slab Geometry
K. Neshat, C. E. Siewert, Y. Ishiguro
Nuclear Science and Engineering | Volume 62 | Number 2 | February 1977 | Pages 330-332
Technical Note | doi.org/10.13182/NSE77-A26968
Asymptotic Solutions in Neutron Transport Theory
V. C. Boffi, V. G. Molinari, G. Spiga
Nuclear Science and Engineering | Volume 62 | Number 2 | February 1977 | Pages 332-339
Technical Note | doi.org/10.13182/NSE77-A26969
New Developments in Generalized Perturbation Methods in the Nuclide Field
A. Gandini, M. Salvatores, L. Tondinelli
Nuclear Science and Engineering | Volume 62 | Number 2 | February 1977 | Pages 339-345
Technical Note | doi.org/10.13182/NSE77-A26970

Number 3

Table of Contents
SPAR1 (O. J. Wallace)

Exact Statistical Analysis of Nonlinear Dynamic Nuclear-Power Reactor Models by the Fokker-Planck Method—Part I: Reactor with Direct Power Feedback
W. L. Dutré, A. F. Debosscher
Nuclear Science and Engineering | Volume 62 | Number 3 | March 1977 | Pages 355-363
Technical Paper | doi.org/10.13182/NSE77-A26977
An Optimal Choice of the Initial Flux for Iterative Solutions of the Inhomogeneous Transport Equation
D. Shalitin, J. J. Wagschal, Y. Yeivin
Nuclear Science and Engineering | Volume 62 | Number 3 | March 1977 | Pages 364-370
Technical Paper | doi.org/10.13182/NSE77-A26978
Finite Element Solutions of the Neutron Transport Equation with Applications to Strong Heterogeneities
William R. Martin, James J. Duderstadt
Nuclear Science and Engineering | Volume 62 | Number 3 | March 1977 | Pages 371-390
Technical Paper | doi.org/10.13182/NSE77-A26979
Ray-Effect Mitigation Methods for Two-Dimensional Neutron Transport Theory
W. F. Miller, Jr., Wm. H. Reed
Nuclear Science and Engineering | Volume 62 | Number 3 | March 1977 | Pages 391-411
Technical Paper | doi.org/10.13182/NSE62-391
Continuous Neutron Slowing Down Theory Applied to Resonances
Meir Segev
Nuclear Science and Engineering | Volume 62 | Number 3 | March 1977 | Pages 412-423
Technical Paper | doi.org/10.13182/NSE77-A26981
Surface Density and Density Analog Models for Criticality in Arrays of Fissile Materials
J. T. Thomas
Nuclear Science and Engineering | Volume 62 | Number 3 | March 1977 | Pages 424-437
Technical Paper | doi.org/10.13182/NSE77-A26982
Revisited
R. J. Howerton
Nuclear Science and Engineering | Volume 62 | Number 3 | March 1977 | Pages 438-454
Technical Paper | doi.org/10.13182/NSE77-A26983
²³⁸U(n, f) Measurements Below 100 keV
R. E. Slovacek, D. S. Cramer, E. B. Bean, J. R. Valentine, R. W. Hockenbury, R. C. Block
Nuclear Science and Engineering | Volume 62 | Number 3 | March 1977 | Pages 455-462
Technical Paper | doi.org/10.13182/NSE77-A26984
Epithermal Neutron Capture in Uranium-238
H. I. Liou, R. E. Chrien
Nuclear Science and Engineering | Volume 62 | Number 3 | March 1977 | Pages 463-478
Technical Paper | doi.org/10.13182/NSE77-A26985
Precise Measurement and Analysis of Neutron Transmission Through Uranium-238
D. K. Olsen, G. de Saussure, R. B. Perez, E. G. Silver, F. C. Difilippo, R. W. Ingle, H. Weaver
Nuclear Science and Engineering | Volume 62 | Number 3 | March 1977 | Pages 479-501
Technical Paper | doi.org/10.13182/NSE77-A26986
Space- and Angle-Dependent Steady-State Thermal-Neutron Spectra Inside Finite Prisms of Graphite
Suresh Garg, Feroz Ahmed, L. S. Kothari
Nuclear Science and Engineering | Volume 62 | Number 3 | March 1977 | Pages 502-510
Technical Paper | doi.org/10.13182/NSE77-A26987
The Half-Life of Cobalt-56
M. E. Anderson
Nuclear Science and Engineering | Volume 62 | Number 3 | March 1977 | Pages 511-514
Technical Paper | doi.org/10.13182/NSE77-A26988
Cross Sections for Gamma-Ray Production by Fast Neutrons for 22 Elements Between Z = 3 and Z = 82
J. K. Dickens, G. L. Morgan, G. T. Chapman, T. A. Love, E. Newman, F. G. Perey
Nuclear Science and Engineering | Volume 62 | Number 3 | March 1977 | Pages 515-531
Technical Paper | doi.org/10.13182/NSE77-A26989
Analysis of Neutron Scattering and Gamma-Ray Production Integral Experiments on Nitrogen for Neutron Energies from 1 to 15 MeV
S. N. Cramer, E. M. Oblow
Nuclear Science and Engineering | Volume 62 | Number 3 | March 1977 | Pages 532-549
Technical Paper | doi.org/10.13182/NSE77-A26990
Measurements and Calculations of the Electron Recoil Spectra from Gamma Rays Emitted by Nitrogen for a 14-MeV Neutron Source
L. F. Hansen, T. Komoto, E. F. Plechaty, B. A. Pohl, G. S. Sidhu, C. Wong
Nuclear Science and Engineering | Volume 62 | Number 3 | March 1977 | Pages 550-558
Technical Paper | doi.org/10.13182/NSE77-A26991
Reactivity Worths of Annular Control Rods in a Pressure-Tube-Type Heavy Water Lattice
Makoto Ueda, Mitsuo Matsumoto, Tohru Haga
Nuclear Science and Engineering | Volume 62 | Number 3 | March 1977 | Pages 559-570
Technical Note | doi.org/10.13182/NSE77-A26992
An Assessment of ENDF/B-IV Data for Uranium-238
Ansar Parvez, Martin Becker
Nuclear Science and Engineering | Volume 62 | Number 3 | March 1977 | Pages 571-574
Technical Note | doi.org/10.13182/NSE77-A26993
Canonical Decoupling and Control of Multiple-Core Nuclear Reactors
S. Tzafestas, N. Chrysochoides
Nuclear Science and Engineering | Volume 62 | Number 3 | March 1977 | Pages 574-579
Technical Note | doi.org/10.13182/NSE77-A26994
A Note on Turbulent-Laminar Transition for Flow in Triangular Rod Bundles
J. W. Yang
Nuclear Science and Engineering | Volume 62 | Number 3 | March 1977 | Pages 579-582
Technical Note | doi.org/10.13182/NSE77-A26995

Number 4

Table of Contents
Nuclear Structure, Vol. II: Nuclear Deformations (L. W. Nordheim)
Of Acceptable Risk: Science and the Determination of Safety (Roy Reider)
Environmental Aspects of Nuclear Power (Bernard L. Cohen)
Random Processes in Nuclear Reactors (Joseph A. Thie)
A Rational Finite Element Basis (J. P. Hennart)
FLASH6 (J. J. Beyer, W. D. Peterson, D. A. Prelewicz, G. W. Swartele)

Neutronics of a Dense-Plasma Focus— An Investigation of a Fusion Plasma
P. Cloth, H. Conrads
Nuclear Science and Engineering | Volume 62 | Number 4 | April 1977 | Pages 591-600
Technical Paper | doi.org/10.13182/NSE77-A15203
The Influence of Design Variations on Controlled Thermonuclear Reactor Blanket Neutronic Performance Using Variational Techniques
Edward T. Cheng, Robert W. Conn
Nuclear Science and Engineering | Volume 62 | Number 4 | April 1977 | Pages 601-616
Technical Paper | doi.org/10.13182/NSE77-A15204
Monte Carlo Shielding Calculations Using Event-Value Path-Length Biasing
J. S. Tang, T. J. Hoffman, P. N. Stevens
Nuclear Science and Engineering | Volume 62 | Number 4 | April 1977 | Pages 617-626
Technical Paper | doi.org/10.13182/NSE77-A15205
Delayed Neutron Yield Calculations for the Neutron-Induced Fission of Uranium-235 as a Function of the Incident Neutron Energy
D. R. Alexander, M. S. Krick
Nuclear Science and Engineering | Volume 62 | Number 4 | April 1977 | Pages 627-635
Technical Paper | doi.org/10.13182/NSE77-A15206
Measured Near-Equilibrium Delayed Neutron Spectra Produced by Fast-Neutron-Induced Fission of ²³²Th, ²³³U, ²³⁵U, ²³⁸U, and ²³⁹Pu
George W. Eccleston, Gene L. Woodruff
Nuclear Science and Engineering | Volume 62 | Number 4 | April 1977 | Pages 636-651
Technical Paper | doi.org/10.13182/NSE77-A15207
Equilibrium Delayed Neutron Spectra from Fast Fission of Uranium-235, Uranium-238, and Plutonium-239
Albert E. Evans, M. S. Krick
Nuclear Science and Engineering | Volume 62 | Number 4 | April 1977 | Pages 652-659
Technical Paper | doi.org/10.13182/NSE77-A15208
Evaluated Delayed Neutron Spectra and Their Importance in Reactor Calculations
D. Saphier, D. Ilberg, S. Shalev, S. Yiftah
Nuclear Science and Engineering | Volume 62 | Number 4 | April 1977 | Pages 660-694
Technical Paper | doi.org/10.13182/NSE77-A15209
An Experimental Study of the Prompt Fission Neutron Spectrum Induced by 0.5-MeV Neutrons Incident on Uranium-235
P. I. Johansson, B. Holmqvist
Nuclear Science and Engineering | Volume 62 | Number 4 | April 1977 | Pages 695-708
Technical Paper | doi.org/10.13182/NSE77-A15210
An Improved Response Matrix Method for Calculating Neutron Flux Distributions
Toshikazu Takeda, Kazuo Azekura, Tadahiro Ohnishi
Nuclear Science and Engineering | Volume 62 | Number 4 | April 1977 | Pages 709-715
Technical Paper | doi.org/10.13182/NSE77-A15211
Gamma-Ray Production Cross Sections for Copper from 0.67 to 19.6 MeV
V. C. Rogers, D. R. Dixon, C. G. Hoot, D. Costello, V. J. Orphan
Nuclear Science and Engineering | Volume 62 | Number 4 | April 1977 | Pages 716-725
Technical Paper | doi.org/10.13182/NSE77-A15212
Effect of Fixed and Soluble Neutron Absorbers on the Criticality of Uranium-Plutonium Systems
R. C. Lloyd, E. D. Clayton
Nuclear Science and Engineering | Volume 62 | Number 4 | April 1977 | Pages 726-735
Technical Paper | doi.org/10.13182/NSE77-A15213
Taylor Coefficients for Eisenhauer-Simmons Gamma-Ray Buildup Factors in Ordinary Concrete
K. Shure, O. J. Wallace
Nuclear Science and Engineering | Volume 62 | Number 4 | April 1977 | Pages 736-738
Technical Note | doi.org/10.13182/NSE77-A15214
A Low-Order Approximation for Highly Anisotropic Multigroup Transport Cross Sections
Wayne J. Mikols, J. Kenneth Shultis
Nuclear Science and Engineering | Volume 62 | Number 4 | April 1977 | Pages 738-743
Technical Note | doi.org/10.13182/NSE77-A15215
Neutron Spectrum in a Heavy Gas
Raymond L. Murray, Reed S. C. Rogers, Saber Musazay
Nuclear Science and Engineering | Volume 62 | Number 4 | April 1977 | Pages 743-745
Technical Note | doi.org/10.13182/NSE77-A15216
Neutron Diffusion in Finite Blocks of Beryllium
A. N. Verma, Feroz Ahmed, L. S. Kothari
Nuclear Science and Engineering | Volume 62 | Number 4 | April 1977 | Pages 745-750
Technical Note | doi.org/10.13182/NSE77-A15217
A Coarse-Mesh Method for Multidimensional, Mixed-Lattice Diffusion Calculations
H. L. Dodds, Jr., H. C. Honeck, D. E. Hostetler
Nuclear Science and Engineering | Volume 62 | Number 4 | April 1977 | Pages 751-756
Technical Note | doi.org/10.13182/NSE77-A15218
Some Properties of the Width Fluctuation Factor
H. Gruppelaar, G. Reffo
Nuclear Science and Engineering | Volume 62 | Number 4 | April 1977 | Pages 756-763
Technical Note | doi.org/10.13182/NSE77-A15219
Nuclear Reactor Control Using Walsh Function Variational Synthesis
S. Tzafestas, N. Chrysochoides
Nuclear Science and Engineering | Volume 62 | Number 4 | April 1977 | Pages 763-770
Technical Note | doi.org/10.13182/NSE77-A15220