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.
Membership
- Explore membership for yourself or for your organization.
Events
- Conference Spotlight
  Nuclear Energy Conference & Expo (NECX)
  September 8–11, 2025
  Atlanta, GA|Atlanta Marriott Marquis
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
  Jul 2025
  Jan 2025
  Latest Journal Issues
  Nuclear Science and Engineering
  September 2025
  Nuclear Technology
  August 2025
  Fusion Science and Technology
  August 2025
- Latest News
  Inkjet droplets of radioactive material enable quick, precise testing at NIST
  Researchers at the National Institute of Standards and Technology have developed a technique called cryogenic decay energy spectrometry capable of detecting single radioactive decay events from tiny material samples and simultaneously identifying the atoms involved. In time, the technology could replace characterization tasks that have taken months and could support rapid, accurate radiopharmaceutical development and used nuclear fuel recycling, according to an article published on July 8 by NIST.
Search

Jump to:

Number 1
Number 2

Number 3
Number 4

Number 1

Table of Contents
Annual Review of Nuclear Science (William G. Pollard)
Symposium on Cooling Tower Environment—1974 (T. Shapiro)
Energy: Historical Development of the Concept (E. Scott Barr)

Numerical Calculation of Two-Phase Flows
John R. Travis, Francis H. Harlow, Anthony A. Amsden
Nuclear Science and Engineering | Volume 61 | Number 1 | September 1976 | Pages 1-10
Technical Paper | doi.org/10.13182/NSE76-A28455
Models for Calculating the Effects of Isotopic Exchange, Radioactive Decay, and Recycle in Removing Iodine from Gas and Liquid Streams
Wallace Davis, Jr.
Nuclear Science and Engineering | Volume 61 | Number 1 | September 1976 | Pages 11-20
Technical Paper | doi.org/10.13182/NSE76-A28456
Radiation-Damage Calculations: Primary Knock-On Atom Spectra, Displacement Rates, and Gas Production Rates
T. A. Gabriel, J. D. Amburgey, N. M. Greene
Nuclear Science and Engineering | Volume 61 | Number 1 | September 1976 | Pages 21-32
Technical Paper | doi.org/10.13182/NSE76-A28457
Neutron Spectrum from a Uranium-235 Sphere Bombarded by 14-MeV Neutrons
C. E. Ragan III, G. F. Auchampaugh, A. Hemmendinger, M. G. Silbert
Nuclear Science and Engineering | Volume 61 | Number 1 | September 1976 | Pages 33-39
Technical Paper | doi.org/10.13182/NSE76-A28458
Cross Sections for the Production of 8- to 20-MeV Photons
G. Longo, F. Saporetti
Nuclear Science and Engineering | Volume 61 | Number 1 | September 1976 | Pages 40-52
Technical Paper | doi.org/10.13182/NSE76-A28459
Reaction Rates in a Uranium Pile Surrounding a 14-MeV Neutron Source: Calculations of the Weale Experiment
R. C. Haight, J. D. Lee, J. A. Maniscalco
Nuclear Science and Engineering | Volume 61 | Number 1 | September 1976 | Pages 53-59
Technical Paper | doi.org/10.13182/NSE76-A28460
The Kinetics of a Coupled Two-Core Nuclear Reactor
Felix C. Difilippo, Ricardo M. Waldman
Nuclear Science and Engineering | Volume 61 | Number 1 | September 1976 | Pages 60-71
Technical Paper | doi.org/10.13182/NSE76-A28461
Neutron Transport in Two Dissimilar Media with Anisotropic Scattering
A. R. Burkart, Y. Ishiguro, C. E. Siewert
Nuclear Science and Engineering | Volume 61 | Number 1 | September 1976 | Pages 72-77
Technical Paper | doi.org/10.13182/NSE76-A28462
Thermal-Neutron Transport Processes in H₂O-D₂O Mixtures in the Temperature Range 253 to 21 K: The Possible Use of These Moderators as Cold-Neutron Sources
G. S. Gangwani, S. P. Tewari, L. S. Kothari
Nuclear Science and Engineering | Volume 61 | Number 1 | September 1976 | Pages 78-89
Technical Paper | doi.org/10.13182/NSE76-A28463
The Application of Neutron Transport Codes to the Transport of Neutrals in Plasmas
J. H. Marable, E. M. Oblow
Nuclear Science and Engineering | Volume 61 | Number 1 | September 1976 | Pages 90-97
Technical Paper | doi.org/10.13182/NSE76-A28464
Analysis of the Coarse-Mesh Rebalancing Effect on Chebyshev Polynomial Iterations
S. Nakamura
Nuclear Science and Engineering | Volume 61 | Number 1 | September 1976 | Pages 98-106
Technical Paper | doi.org/10.13182/NSE76-A28465
Mass Transfer in the Contamination of Isothermal Steel Surfaces
D. H. Lister
Nuclear Science and Engineering | Volume 61 | Number 1 | September 1976 | Pages 107-112
Technical Note | doi.org/10.13182/NSE76-A28466
A Low Reynolds Number Bundle-Size Effect for Wire-Wrapped Liquid-Metal Fast Breeder Reactor Assemblies
Ehsan U. Khan
Nuclear Science and Engineering | Volume 61 | Number 1 | September 1976 | Pages 112-115
Technical Note | doi.org/10.13182/NSE76-A28467
The Energy Dependence of the Neutron Absorption and Fission Cross Sections of U ranium-235 and Plutonium-239 Below 1 eV and the Wescott g Factors
R. Gwin
Nuclear Science and Engineering | Volume 61 | Number 1 | September 1976 | Pages 116-117
Technical Note | doi.org/10.13182/NSE76-A28468
A Two-Dimensional Time-Dependent Neutron Transport Calculation Using One-Dimensional Equations
Michael Boring, W. H. Roach
Nuclear Science and Engineering | Volume 61 | Number 1 | September 1976 | Pages 117-118
Technical Note | doi.org/10.13182/NSE76-A28469

Number 2

Table of Contents
Comments on the Probability Table Method (M. N. Nikolaev)
CYLTRAN (Edward Larsen, W. H. Vandevender)
Thermodynamics of Linear Transport Processes (Edward Larsen)
The Equations of Radiation Hydrodynamics

A Coarse-Mesh Correction of the Finite Difference Method for Neutron Diffusion Calculations
Yasuyoshi Kato, Toshikazu Takeda, Seiichi Takeda
Nuclear Science and Engineering | Volume 61 | Number 2 | October 1976 | Pages 127-141
Technical Paper | doi.org/10.13182/NSE76-A27347
Exact Solutions of the Neutron Slowing Down Equation
Trine-Yie Dawn, Chio-Min Yang
Nuclear Science and Engineering | Volume 61 | Number 2 | October 1976 | Pages 142-158
Technical Paper | doi.org/10.13182/NSE76-A27348
A Discrete Energy Formulation of Neutron Transport Theory Applied to Solving the Discrete Ordinates Equations
J. Ching, E. M. Oblow, H. Goldstein
Nuclear Science and Engineering | Volume 61 | Number 2 | October 1976 | Pages 159-169
Technical Paper | doi.org/10.13182/NSE76-A27349
Perturbation Theory and Importance Functions in Integral Transport Formulations
E. Greenspan
Nuclear Science and Engineering | Volume 61 | Number 2 | October 1976 | Pages 170-180
Technical Paper | doi.org/10.13182/NSE76-A27350
The Representation of Light-Water Reflectors by Boundary Conditions
P.C. Kalambokas, A. F. Henry
Nuclear Science and Engineering | Volume 61 | Number 2 | October 1976 | Pages 181-194
Technical Paper | doi.org/10.13182/NSE76-A27351
External Bremsstrahlung Generated by Yttrium-91 and Thallium-204 Beta Rays
K. V. N. Sarma, K. Narasimha Murty, V. V. V. Subrahmanyam
Nuclear Science and Engineering | Volume 61 | Number 2 | October 1976 | Pages 195-200
Technical Paper | doi.org/10.13182/NSE76-A27352
Calculations of the Neutron Emission Spectra from Materials Bombarded with 14-MeV Neutrons
L. F. Hansen, S. M. Grimes, R. J. Howerton, J D. Anderson
Nuclear Science and Engineering | Volume 61 | Number 2 | October 1976 | Pages 201-211
Technical Paper | doi.org/10.13182/NSE76-A27353
The Transmutation of Strontium-90 and Cesium-137 in a High-Flux Fast Reactor with a Thermalized Central Region
M. Taube
Nuclear Science and Engineering | Volume 61 | Number 2 | October 1976 | Pages 212-221
Technical Paper | doi.org/10.13182/NSE76-A27354
Postaccident Heat Removal—Part I: Heat Transfer Within an Internally Heated, Nonboiling Liquid Layer
Louis Baker, Jr., Richard E. Faw, Francis A. Kulacki
Nuclear Science and Engineering | Volume 61 | Number 2 | October 1976 | Pages 222-230
Technical Paper | doi.org/10.13182/NSE76-A27355
Postaccident Heat Removal—Part II: Heat Transfer from an Internally Heated Liquid to a Melting Solid
Richard E. Faw, Louis Baker, Jr.
Nuclear Science and Engineering | Volume 61 | Number 2 | October 1976 | Pages 231-238
Technical Paper | doi.org/10.13182/NSE76-A27356
Solution of the Fuel Burnup Control Problem with a Controlling Neutron Equation and Walsh Functions
Ryuji Koga
Nuclear Science and Engineering | Volume 61 | Number 2 | October 1976 | Pages 239-249
Technical Paper | doi.org/10.13182/NSE76-A27357
On the Dynamics of Transition Region Flow Boiling
W. C. Peterson, M. G. Zaalouk, S. İ. Güçeri
Nuclear Science and Engineering | Volume 61 | Number 2 | October 1976 | Pages 250-257
Technical Paper | doi.org/10.13182/NSE76-A27358
A Groupwise Rebalancing Technique for Integral Transport Problems
Hsiang-Shou Cheng
Nuclear Science and Engineering | Volume 61 | Number 2 | October 1976 | Pages 258-261
Technical Note | doi.org/10.13182/NSE76-A27359
Two-Dimensional Calculation of a Pulse Propagation Experiment
J. M. A. Christens, P. B. Parks, N. J. Diaz
Nuclear Science and Engineering | Volume 61 | Number 2 | October 1976 | Pages 261-267
Technical Note | doi.org/10.13182/NSE76-A27360
Cross Section for the ⁹Be(n, t₁)⁷Li Reaction Between 13.3 and 15 MeV
F. S. Dietrich, L. F. Hansen, R. P. Koopman
Nuclear Science and Engineering | Volume 61 | Number 2 | October 1976 | Pages 267-268
Technical Note | doi.org/10.13182/NSE76-A27361
Geometrical Efficiency Equation for Proton Recoil Telescopes
G. E. Hansen, R. K. Smith, G. G. Simons
Nuclear Science and Engineering | Volume 61 | Number 2 | October 1976 | Pages 269-276
Technical Note | doi.org/10.13182/NSE76-A27362
Nonlinear Dynamics of a Pressurized Water Reactor Core
R. J. Onega, K. E. Karcher
Nuclear Science and Engineering | Volume 61 | Number 2 | October 1976 | Pages 276-282
Technical Note | doi.org/10.13182/NSE76-A27363
Laminar-Flow Pressure Drop in Symmetrical Finite Rod Bundles
John P. Zarling
Nuclear Science and Engineering | Volume 61 | Number 2 | October 1976 | Pages 282-285
Technical Note | doi.org/10.13182/NSE76-A27364

Number 3

Table of Contents

Two-Phase Pressure Drop Across Abrupt Area Changes in Oscillatory Flow
J. Weisman, T. Ake, R. Knott
Nuclear Science and Engineering | Volume 61 | Number 3 | November 1976 | Pages 297-309
Technical Paper | doi.org/10.13182/NSE76-A26916
Transient Freezing of a Flowing Ceramic Fuel in a Steel Channel
Michael Epstein, Michael A. Grolmes, Robert E. Henry, Hans K. Fauske
Nuclear Science and Engineering | Volume 61 | Number 3 | November 1976 | Pages 310-323
Technical Paper | doi.org/10.13182/NSE76-A26917
Experimental Development of Design Criteria to Limit Liquid Cross-Flow-Induced Vibration in Nuclear Reactor Heat Exchange Equipment
D. J. Gorman
Nuclear Science and Engineering | Volume 61 | Number 3 | November 1976 | Pages 324-336
Technical Paper | doi.org/10.13182/NSE76-A26918
Cross Sections for the Al(n, xn) and Al(n, xγ) Reactions Between 1 and 20 MeV
G. L. Morgan, F. G. Perey
Nuclear Science and Engineering | Volume 61 | Number 3 | November 1976 | Pages 337-345
Technical Paper | doi.org/10.13182/NSE76-A26919
Neutron Capture Cross Section of Cobalt-59 in the Energy Range 2.5 to 1000 keV
R. R. Spencer, R. L. Macklin
Nuclear Science and Engineering | Volume 61 | Number 3 | November 1976 | Pages 346-355
Technical Paper | doi.org/10.13182/NSE76-A26920
Neutron Absorption Cross Section of Americium-241
L. W. Weston, J. H. Todd
Nuclear Science and Engineering | Volume 61 | Number 3 | November 1976 | Pages 356-365
Technical Paper | doi.org/10.13182/NSE76-A26921
Light Charged Particles and Fission Elements from Californium-252 Fission
Charles A. Bolig, Jr., R. R. Roy
Nuclear Science and Engineering | Volume 61 | Number 3 | November 1976 | Pages 366-369
Technical Paper | doi.org/10.13182/NSE76-A26922
Critical Experiments with Low-Moderated Homogeneous Mixtures of Plutonium and Uranium Oxides Containing 8, 15, and 30 wt% Plutonium
S. R. Bierman, E. D. Clayton
Nuclear Science and Engineering | Volume 61 | Number 3 | November 1976 | Pages 370-376
Technical Paper | doi.org/10.13182/NSE76-A26923
A Simple Approximate Treatment of Neutron Inelastic Scattering in a Fast Reactor Assembly
Yasunori Yamamura
Nuclear Science and Engineering | Volume 61 | Number 3 | November 1976 | Pages 377-387
Technical Paper | doi.org/10.13182/NSE76-A26924
Synthesis of an Elementary Function for the Spatially Dependent Neutron Slowing Down Distribution in Hydrogen
Harvey J. Amster, K. Cheuk Chan
Nuclear Science and Engineering | Volume 61 | Number 3 | November 1976 | Pages 388-398
Technical Paper | doi.org/10.13182/NSE76-A26925
Stability Analysis of Spatially Dependent Nonlinear Reactor Systems Using a Semigroup Approach
Ronald J. Onega, Lech Mync, John A. Burns
Nuclear Science and Engineering | Volume 61 | Number 3 | November 1976 | Pages 399-407
Technical Paper | doi.org/10.13182/NSE76-A26926
A Method of Characteristics and Other Improvements in Solution Methods for the Transport Equation
Bengt G. Carlson
Nuclear Science and Engineering | Volume 61 | Number 3 | November 1976 | Pages 408-425
Technical Paper | doi.org/10.13182/NSE76-A26927
Observation of a Difference in Yields of Delayed Neutron Emitters from U₃O₈ and UO₂
H. R. Lukens, R. L. Bramblett
Nuclear Science and Engineering | Volume 61 | Number 3 | November 1976 | Pages 426-428
Technical Note | doi.org/10.13182/NSE76-A26928
Critical Experiments and the 2200 m/sec Neutron Parameters
R. Gwin
Nuclear Science and Engineering | Volume 61 | Number 3 | November 1976 | Pages 428-431
Technical Note | doi.org/10.13182/NSE76-A26929
Acceleration of the Convergence of the Integral Transform Method
V. C. Boffi, V. G. Molinari, G. Spiga
Nuclear Science and Engineering | Volume 61 | Number 3 | November 1976 | Pages 431-434
Technical Note | doi.org/10.13182/NSE76-A26930
Generalized Exact Spatially Dependent Neutron Slowing Down Distribution Near Source Lethargy
K. Cheuk Chan, Harvey J. Amster
Nuclear Science and Engineering | Volume 61 | Number 3 | November 1976 | Pages 434-437
Technical Note | doi.org/10.13182/NSE76-A26931
Control Algorithms in a Coarse-Mesh Rebalance Framework
M. V. Gregory, H. C. Honeck
Nuclear Science and Engineering | Volume 61 | Number 3 | November 1976 | Pages 437-445
Technical Note | doi.org/10.13182/NSE76-A26932

Number 4

Table of Contents
Corrigendum (Felix C. Difilippo, Ricardo M. Waldman)

An Early-Time Analysis of Space-Dependent Nuclear Reactor Transients
S. L. Paveri-Fontana, P. L. Chambré
Nuclear Science and Engineering | Volume 61 | Number 4 | December 1976 | Pages 451-465
Technical Paper | doi.org/10.13182/NSE76-A14482
Reactor-Fuel-Independent Reactivity Determinations
S. Pearlstein
Nuclear Science and Engineering | Volume 61 | Number 4 | December 1976 | Pages 466-470
Technical Paper | doi.org/10.13182/NSE76-A14483
Measurement of the Ratio of Fission to Capture Neutron Cross Sections in Uranium-235 in the 200-eV to 15-keV Energy Range
H. Bluhm, C. S. Yen
Nuclear Science and Engineering | Volume 61 | Number 4 | December 1976 | Pages 471-476
Technical Paper | doi.org/10.13182/NSE76-A14484
Fission Cross Section of Neptunium-237 from 3 eV to 2 MeV
S. Plattard, J. Blons, D. Paya
Nuclear Science and Engineering | Volume 61 | Number 4 | December 1976 | Pages 477-495
Technical Paper | doi.org/10.13182/NSE76-A14485
The ENDF/B-IV Representation of the Uranium-238, Total Neutron Cross Section in the Resolved Resonance Energy Region
G. de Saussure, D. K. Olsen, R. B. Perez
Nuclear Science and Engineering | Volume 61 | Number 4 | December 1976 | Pages 496-506
Technical Paper | doi.org/10.13182/NSE76-A14486
Measurement of the Angular Neutron Energy Spectra Originating from a 14-MeV Neutron Source in Liquid Air
K. Clausen, B. Bröcker, P. Schneider-Kühnle, M. Weinert
Nuclear Science and Engineering | Volume 61 | Number 4 | December 1976 | Pages 507-520
Technical Paper | doi.org/10.13182/NSE76-A14487
Differential Elastic and Inelastic Scattering of 9- to 15-MeV Neutrons from Carbon
D. W. Glasgow, F. O. Purser, H. Hogue, J. C. Clement, K. Stelzer, G. Mack, J. R. Boyce, D. H. Epperson, S. G. Buccino, P. W. Lisowski, S. G. Glendinning, E. G. Bilpuch, H. W. Newson, C. R. Gould
Nuclear Science and Engineering | Volume 61 | Number 4 | December 1976 | Pages 521-533
Technical Paper | doi.org/10.13182/NSE76-A14488
Spherical Harmonics Approximations of Neutron Transport
A. Demény, K. M. Dede, K. Erdei
Nuclear Science and Engineering | Volume 61 | Number 4 | December 1976 | Pages 534-535
Technical Note | doi.org/10.13182/NSE76-A14489
A Numerical Method for Solving the Integral Equation of Neutron Transport: III
Robert W. Tsai, Sudarshan K. Loyalka
Nuclear Science and Engineering | Volume 61 | Number 4 | December 1976 | Pages 536-540
Technical Note | doi.org/10.13182/NSE76-A14490
Measurement of Cross Sections for the ⁷Li(n, n′γ)⁷Li Reaction from 0.57 to 4 MeV
Donald L. Smith
Nuclear Science and Engineering | Volume 61 | Number 4 | December 1976 | Pages 540-543
Technical Note | doi.org/10.13182/NSE76-A14491
Rational Approximations for Cross-Section Space-Shielding in Doubly Heterogeneous Systems
M. G. Stamatelatos
Nuclear Science and Engineering | Volume 61 | Number 4 | December 1976 | Pages 543-549
Technical Note | doi.org/10.13182/NSE76-A14492
Basic Collapse Criteria for Boiling Reactor-Fuel-Steel Mixtures
Paul B. Abramson
Nuclear Science and Engineering | Volume 61 | Number 4 | December 1976 | Pages 549-552
Technical Note | doi.org/10.13182/NSE76-A14493