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
  Materials Science & Technology
  The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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
  February 2025
  Fusion Science and Technology
  February 2025
- Latest News
  IEA report: Challenges need to be resolved to support global nuclear energy growth
  The International Energy Agency published a new report this month outlining how continued innovation, government support, and new business models can unleash nuclear power expansion worldwide.
  The Path to a New Era for Nuclear Energy report “reviews the status of nuclear energy around the world and explores risks related to policies, construction, and financing.”
  Find the full report at IEA.org.
Search

Jump to:

Number 1
Number 2

Number 3
Number 4

Number 1

Table of Contents
A Note on a Simple Method for Acceleration of Finite-Difference Group-Diffusion Calculations (Melvin Tobias, David R. Vondy, Tom B. Fowler)
DancofF Correction for Several Infinitely Long Cylindrical Rings (G. Velarde)
Neutron Absorber Materials for Reactor Control. (John R. Weeks)
The Metal Plutonium. (James F. Schumar)
Selected Papers on New Techniques for Energy Conversion. (R. L. Mela)
ZORCH (C. W. Nestor, Jr.)
GMCM-9 (M. J. Kniedler)

On the Theory of Space Dependent Neutron Spectra in Heterogeneous Reactors
Helmut Kunze
Nuclear Science and Engineering | Volume 15 | Number 1 | January 1963 | Pages 1-12
Technical Paper | doi.org/10.13182/NSE63-A26258
The Time Decay Constants in Neutron Thermalization
Noel Corngold, Paul Michael, Warren Wollman
Nuclear Science and Engineering | Volume 15 | Number 1 | January 1963 | Pages 13-19
Technical Paper | doi.org/10.13182/NSE63-A26259
Interaction of Fissionable Units
Hugh K. Clark
Nuclear Science and Engineering | Volume 15 | Number 1 | January 1963 | Pages 20-28
Technical Paper | doi.org/10.13182/NSE63-A26260
The Thermal Utilization and Flux Ratios in Complex Lattices
A. PAZY
Nuclear Science and Engineering | Volume 15 | Number 1 | January 1963 | Pages 29-36
Technical Paper | doi.org/10.13182/NSE63-A26261
Self-Limiting Power Excursion Tests of a Water-Moderated Low-Enrichment UO₂ Core
A. H. Spano
Nuclear Science and Engineering | Volume 15 | Number 1 | January 1963 | Pages 37-51
Technical Paper | doi.org/10.13182/NSE63-A26262
Equations for Bilateral Heat Transfer to a Fluid Flowing in a Concentric Annulus
O. E. Dwyer
Nuclear Science and Engineering | Volume 15 | Number 1 | January 1963 | Pages 52-57
Technical Paper | doi.org/10.13182/NSE63-A26263
Unilateral Heat Transfer to Liquid Metals Flowing in Annuli
O.E. Dwyer, P. S. Tu
Nuclear Science and Engineering | Volume 15 | Number 1 | January 1963 | Pages 58-68
Technical Paper | doi.org/10.13182/NSE63-A26264
Low Temperature Galvanomagnetic Properties of Graphites
G. L. Montet
Nuclear Science and Engineering | Volume 15 | Number 1 | January 1963 | Pages 69-80
Technical Paper | doi.org/10.13182/NSE63-A26265
Energy Deposition by Fast Neutrons: NO₂ Production in Liquid Air
Robert C. Axtmann, John, Bridgwater
Nuclear Science and Engineering | Volume 15 | Number 1 | January 1963 | Pages 81-89
Technical Paper | doi.org/10.13182/NSE63-A26266
Deuterium Enrichment in the Distillation of Ammonia
Gerald, T. Petersen, Manson, Benedict
Nuclear Science and Engineering | Volume 15 | Number 1 | January 1963 | Pages 90-97
Technical Paper | doi.org/10.13182/NSE63-A26267

Number 2

Table of Contents
An Upper Limit for the Effective Capture Cross Section of Po²¹⁰ for Thermal Neutrons (J. Halperin, J. H. Oliver)
Radiation Damage to Freon-11, CCI₃F (M. D. Silverman, B. O. Heston, P. S. Rudolph)
Determinations of the Total Emissivity of Polished and Oxidized Uranium Surfaces (L. Baker, Jr., E. M. Mouradian, J. D. Bingle)
Note on Spectrum Hardening for Non 1/v Cross Sections (W. Clendenin)
The Time Scale of Neutron Slowing Down in Water (E. Möller,, N. G. SjöStrand)
Space Research II: Proceedings of the Second International Space Science Symposium, Florence, April 10–14, 1961 (Herbert Goldstein)
Nuclear Propulsion for Merchant Ships (Wm. B. Cottrell)
Tritium in the Physical and Biological Sciences (D. E. Hull, B. A. Fries)
Physics of Fast and Intermediate Reactors, Volume II (M. M. Levine)
EQUIPOISE BURNOUT (D. R. Vondy, T. B. Fowler)
Erratum: A New Method for Measuring Thermalization Parameters

Elementary Methods of Reactor Noise Analysis
Joseph A. Thie
Nuclear Science and Engineering | Volume 15 | Number 2 | February 1963 | Pages 109-114
Technical Paper | doi.org/10.13182/NSE63-A26408
The Angular Dependence of Thermal Neutron Spectra in Lattices
Henry C. Honeck, Hiroshi Takahashi
Nuclear Science and Engineering | Volume 15 | Number 2 | February 1963 | Pages 115-123
Technical Paper | doi.org/10.13182/NSE63-A26409
Behavior of Iodine and Xenon in the Homogeneous Reactor Test
William D. Burch, Lawrence B. Shappert
Nuclear Science and Engineering | Volume 15 | Number 2 | February 1963 | Pages 124-130
Technical Paper | doi.org/10.13182/NSE63-A26410
At-Power, Low-Frequency, Reactor-Power-Spectrum Measurements and Comparison with Oscillation Measurements
C.W. Griffin, R. L. Randall
Nuclear Science and Engineering | Volume 15 | Number 2 | February 1963 | Pages 131-138
Technical Paper | doi.org/10.13182/NSE63-A26411
Adjoint Functions and Orthogonality Relations
K. F. Hansen, M. Clark, Jr.
Nuclear Science and Engineering | Volume 15 | Number 2 | February 1963 | Pages 139-141
Technical Paper | doi.org/10.13182/NSE63-A26412
Generalized Quota Sampling
Herbert A. Steinberg
Nuclear Science and Engineering | Volume 15 | Number 2 | February 1963 | Pages 142-145
Technical Paper | doi.org/10.13182/NSE63-A26413
Measurements of the Temperature Coefficient of Resonance Absorption in Uranium Metal and Uranium Oxide
B.L. Palowitch, F. S. Frantz, Jr.
Nuclear Science and Engineering | Volume 15 | Number 2 | February 1963 | Pages 146-157
Technical Paper | doi.org/10.13182/NSE63-A26414
The Transport Approximation of the Energy-Dependent Boltzmann Equation
G. Rakavy, Y. Yeivin
Nuclear Science and Engineering | Volume 15 | Number 2 | February 1963 | Pages 158-160
Technical Paper | doi.org/10.13182/NSE63-A26415
Convergence Improvement of Disadvantage Factors by the Use of Even Order Spherical Harmonics Approximations
John O. Mingle
Nuclear Science and Engineering | Volume 15 | Number 2 | February 1963 | Pages 161-165
Technical Paper | doi.org/10.13182/NSE63-A26416
Kinetics of Low Source Reactor Startups. Part I
H. Hurwitz, Jr., D. B. MacMillan, J. H. Smith, M. L. Storm
Nuclear Science and Engineering | Volume 15 | Number 2 | February 1963 | Pages 166-186
Technical Paper | doi.org/10.13182/NSE63-3
Kinetics of Low Source Reactor Startups. Part II
H. Hurwitz, Jr.
Nuclear Science and Engineering | Volume 15 | Number 2 | February 1963 | Pages 187-196
Technical Paper | doi.org/10.13182/NSE63-4
Linear Stability of the Thermal Flux in a Reflected Core Containing Xenon and Temperature Reactivity Feedback
Louis M. Shotkin, Frederick H. Abernathy
Nuclear Science and Engineering | Volume 15 | Number 2 | February 1963 | Pages 197-212
Technical Paper | doi.org/10.13182/NSE63-A26419
Average Number of Prompt Neutrons Emitted in the Spontaneous Fission of U²³⁸ and Pu²⁴⁰
I. Asplund-Nilsson, H. Condé, N. Starfelt
Nuclear Science and Engineering | Volume 15 | Number 2 | February 1963 | Pages 213-216
Technical Paper | doi.org/10.13182/NSE63-A26420

Number 3

Table of Contents
Xenon Poisoning in a Shut-Down Reactor (H. Albers, Z. J. Doron, W. Hälg S. Ravani)
Nonperturbing Foils-An Experimental Verification (J. D. Randall, J. V. Walker)
Beta Decay for Pedestrians (Rudolph Sher)

A Comment on the Collision Density at Epithermal Energies
Coleridge A. Wilkins, A. Keane
Nuclear Science and Engineering | Volume 15 | Number 3 | March 1963 | Pages 229-232
Technical Paper | doi.org/10.13182/NSE63-A26433
The Measurement of the Lattice Parameters of a Gas Cooled Reactor Lattice
P. F. Nichols, J. R. Worden, F. C. Engesser, R. E. Heineman
Nuclear Science and Engineering | Volume 15 | Number 3 | March 1963 | Pages 233-244
Technical Paper | doi.org/10.13182/NSE63-A26434
A Discussion of Theoretical Analyses of Probe-Induced Thermal Flux Perturbations
R. K. Osborn
Nuclear Science and Engineering | Volume 15 | Number 3 | March 1963 | Pages 245-258
Technical Paper | doi.org/10.13182/NSE63-A26435
Application of the Spherical Harmonics Technique to Problems in Gamma Transport
W. D. Lanning
Nuclear Science and Engineering | Volume 15 | Number 3 | March 1963 | Pages 259-267
Technical Paper | doi.org/10.13182/NSE63-A26436
A Method for the Accurate Determination of Relative Initial Conversion Ratios
P. R. Tunnicliffe, D. J. Skillings, B. G. Chidley
Nuclear Science and Engineering | Volume 15 | Number 3 | March 1963 | Pages 268-283
Technical Paper | doi.org/10.13182/NSE63-A26437
The Mass Spectrometric Determination of the Cs¹³⁷ Half-Life
B.F. Rider, J. P. Peterson, Jr., C. P. Ruiz
Nuclear Science and Engineering | Volume 15 | Number 3 | March 1963 | Pages 284-287
Technical Paper | doi.org/10.13182/NSE63-A26438
Rates and Mechanisms of the Loss of Fission Products from Uranium-Graphite Fuel Materials
E. A. Bryant, G. A. Cowan, J. E. Sattizahn, Kurt Wolfsberg
Nuclear Science and Engineering | Volume 15 | Number 3 | March 1963 | Pages 288-295
Technical Paper | doi.org/10.13182/NSE63-A26439
Time-Dependent Neutron Thermalization for a Bare Multiplying Medium
Edward Garelis
Nuclear Science and Engineering | Volume 15 | Number 3 | March 1963 | Pages 296-304
Technical Paper | doi.org/10.13182/NSE63-A26440
The Effect of Inlet Spacing Deviations on the Flow-Induced Deflections of Flat Plates
J. J. Kane
Nuclear Science and Engineering | Volume 15 | Number 3 | March 1963 | Pages 305-308
Technical Paper | doi.org/10.13182/NSE63-A26441
Thermal Neutron Flux Perturbation Due to Indium Foils in Water
Jack V. Walker, John D. Randall, Ronald C. Stinson, Jr.
Nuclear Science and Engineering | Volume 15 | Number 3 | March 1963 | Pages 309-313
Technical Paper | doi.org/10.13182/NSE63-A26442
Effective Cutoff Energies for Boron, Cadmium, Gadolinium, and Samarium Filters
R. W. Stoughton, J. Halperin
Nuclear Science and Engineering | Volume 15 | Number 3 | March 1963 | Pages 314-324
Technical Paper | doi.org/10.13182/NSE63-A26443
The Neutron Flux Perturbation Due to an Absorbing Foil; A Comparison of Theories and Experiments
G. C. Hanna
Nuclear Science and Engineering | Volume 15 | Number 3 | March 1963 | Pages 325-337
Technical Paper | doi.org/10.13182/NSE63-A26444
Stream Flow Measurement by an Inert Tracer Pulse Technique
R. P. Gardner, J. W. Dunn, III
Nuclear Science and Engineering | Volume 15 | Number 3 | March 1963 | Pages 338-341
Technical Paper | doi.org/10.13182/NSE63-A26445

Number 4

Table of Contents
On the Energy-Dependent Transport Equation (G. C. Summerfield, P. F. Zweifel)
Nuclear Reactor Fuel Elements, Metallurgy and Fabrication (Charles R. Johnson)
Small and Medium Power Reactors, Proceedings of the Vienna Conference, September 1960 (W. Kenneth Davis, Tarsem S. Purewal)
Materials Science and Technology for Advanced Applications (E. Creutz)
Self-Limiting Power Excursion Tests of a Water Moderated Low-Enrichment UO₂ Core (A. H. Spano)
Erratum: Measurements of the Temperature Coefficient of Resonance Absorption in Uranium Metal and Uranium Oxide (B. L. Palowitch, F. S. Feantz, Jr)

Design of a Small Aqueous Homogeneous Breeder Reactor
R. H. Chapman, I. Spiewak, M. L. Tobias, D. R. Vondy
Nuclear Science and Engineering | Volume 15 | Number 4 | April 1963 | Pages 347-353
Technical Paper | doi.org/10.13182/NSE63-A26450
The Mechanism of Extraction by Tributyl Phosphate-n-Hexane Solvents: Part II. Nitric Acid Extraction
Donald R. Olander, Manson Benedict
Nuclear Science and Engineering | Volume 15 | Number 4 | April 1963 | Pages 354-365
Technical Paper | doi.org/10.13182/NSE63-A26451
Some Nuclear-Chemical and Physicochemical Problems in Fission-Product Recoil Separation
Ury Passy, Naftali H. Steiger
Nuclear Science and Engineering | Volume 15 | Number 4 | April 1963 | Pages 366-374
Technical Paper | doi.org/10.13182/NSE63-A26452
The Investigation of Neutron Kinetics and Cross Sections in Fast Nonmoderating Assemblies by the Nanosecond Pulsed Neutron Source Technique
L. E. Beghian, N. C. Rasmussen, R. Thews, J. Weber
Nuclear Science and Engineering | Volume 15 | Number 4 | April 1963 | Pages 375-381
Technical Paper | doi.org/10.13182/NSE63-A26453
Epithermal Neutron Absorption in Slab Lattices
M. Goldsmith
Nuclear Science and Engineering | Volume 15 | Number 4 | April 1963 | Pages 382-387
Technical Paper | doi.org/10.13182/NSE63-A26454
Burning Temperatures of Uranium and Zirconium in Air
Edward M. Mouradian, Louis Baker, Jr.
Nuclear Science and Engineering | Volume 15 | Number 4 | April 1963 | Pages 388-394
Technical Paper | doi.org/10.13182/NSE63-A26455
Burning Velocities of Uranium and Zirconium in Air
L. Leibowitz, L. Baker, Jr., J. G. Schnizlein, L. W. Mishler, J. D. Bingle
Nuclear Science and Engineering | Volume 15 | Number 4 | April 1963 | Pages 395-403
Technical Paper | doi.org/10.13182/NSE63-A26456
The Effect of Halogenated Hydrocarbons on the Burning of Uranium and Zirconium
L. Leibowitz, J. G. Schnizlein, L. W. Mishler
Nuclear Science and Engineering | Volume 15 | Number 4 | April 1963 | Pages 404-410
Technical Paper | doi.org/10.13182/NSE63-A26457
Neutron Radiographic Inspection of Radioactive Irradiated Reactor Fuel Specimens
Harold Berger, W. N. Beck
Nuclear Science and Engineering | Volume 15 | Number 4 | April 1963 | Pages 411-414
Technical Paper | doi.org/10.13182/NSE63-A26458
Equipment Used in the Performance of Experiments in Nuclear Reactors at the Argonne National Laboratory
E. S. Sowa, C. R. Breden, L. W. Fromm, Jr.
Nuclear Science and Engineering | Volume 15 | Number 4 | April 1963 | Pages 415-428
Technical Paper | doi.org/10.13182/NSE63-A26459
Calculation of Partial Differential Scattering Cross Sections for Slow Neutrons
H. L. McMurry
Nuclear Science and Engineering | Volume 15 | Number 4 | April 1963 | Pages 429-437
Technical Paper | doi.org/10.13182/NSE63-A26460
Evaluation of Techniques for Computing Partial Differential Scattering Cross Sections
H. L. McMurry, L. J. Gannon, W. A. Hestir
Nuclear Science and Engineering | Volume 15 | Number 4 | April 1963 | Pages 438-450
Technical Paper | doi.org/10.13182/NSE63-A26461
Solution to the Fission Recoil Energy Deposition In a Slurry by a Monte Carlo Technique
Lawrence R. Steele, Daniel Carson, Charles E. Dryden
Nuclear Science and Engineering | Volume 15 | Number 4 | April 1963 | Pages 451-457
Technical Paper | doi.org/10.13182/NSE63-A26462
Water Decomposition by Fission Fragment Recoil Energy in an Aqueous Slurry of Uranium—Thorium Oxides
Lawrence R. Steele, Sheffield Gordon, Charles E. Dryden
Nuclear Science and Engineering | Volume 15 | Number 4 | April 1963 | Pages 458-467
Technical Paper | doi.org/10.13182/NSE63-A26463
Analysis for Diffusion Theory Flux Peaking at a Sharp Corner
J. H. Smith
Nuclear Science and Engineering | Volume 15 | Number 4 | April 1963 | Pages 468-473
Technical Paper | doi.org/10.13182/NSE63-A26464
A Method for Determination of Spatial Stability
Stig Lundquist, Peter Weissglas
Nuclear Science and Engineering | Volume 15 | Number 4 | April 1963 | Pages 474-475
Technical Paper | doi.org/10.13182/NSE63-A26465