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Number 1

Table of Contents
On the Use of First-Order Perturbation Theory in Interface Shift Problems (J. V. Muralidhar Rao, S. M. Lee)
Reply to “On the Use of First-Order Perturbation Theory in Interface Shift Problems” (G. C. Pomraning, F. Rahnema)
Response to “Comments on ‘The Effects of Intracell Adjoint Flux Heterogeneity on First-Order Perturbation Reactivity Calculations’” (Kord S. Smith)
Comments on “The Effects of Intracell Adjoint Flux Heterogeneity on First-Order Perturbation Reactivity Calculations” (Ehud Greenspan)

Measurement of the ^242mAm Neutron Fission Cross Section
J. W. T. Dabbs, C. E. Bemis, Jr., S. Raman, R. J. Dougan, R. W. Hoff
Nuclear Science and Engineering | Volume 84 | Number 1 | May 1983 | Pages 1-11
Technical Paper | doi.org/10.13182/NSE83-A17453
Neutron-Induced Gamma-Ray Production in ⁵⁷Fe for Incident Neutron Energies Between 0.16 and 21 MeV
Z. W. Bell, J. K. Dickens, D. C. Larson, J. H. Todd
Nuclear Science and Engineering | Volume 84 | Number 1 | May 1983 | Pages 12-32
Technical Paper | doi.org/10.13182/NSE83-A17454
The Solution of the Multigroup Neutron Transport Equation Using Spherical Harmonics
J. K. Fletcher
Nuclear Science and Engineering | Volume 84 | Number 1 | May 1983 | Pages 33-46
Technical Paper | doi.org/10.13182/NSE83-A17455
Thermal Performance Modeling of Sphere-Pac Mixed Carbide Fast Reactor Fuel
M. J. Ades, K. L. Peddicord, S. D. Montgomery
Nuclear Science and Engineering | Volume 84 | Number 1 | May 1983 | Pages 47-58
Technical Note | doi.org/10.13182/NSE83-A17456
Real-Time Nonlinear Estimation of Fuel-Clad Gap Conductance
J. Louis Tylee
Nuclear Science and Engineering | Volume 84 | Number 1 | May 1983 | Pages 58-61
Technical Note | doi.org/10.13182/NSE83-A17457
Benchmark Values for Monoenergetic Neutron Transport in One-Dimensional Cylindrical Geometry with Linearly Anisotropic Scattering
R. Sanchez, B. D. Ganapol
Nuclear Science and Engineering | Volume 84 | Number 1 | May 1983 | Pages 61-66
Technical Note | doi.org/10.13182/NSE83-A17458
Two Vectorized Algorithms for the Solution of Three-Dimensional Neutron Diffusion Equations
Wm. A. Thomas, E. E. Lewis
Nuclear Science and Engineering | Volume 84 | Number 1 | May 1983 | Pages 67-71
Technical Note | doi.org/10.13182/NSE83-A17459

Number 2

Table of Contents

The Critical Problem for an Infinite Cylinder
J. R. Thomas, Jr., J. D. Southers, C. E. Siewert
Nuclear Science and Engineering | Volume 84 | Number 2 | June 1983 | Pages 79-82
Technical Paper | doi.org/10.13182/NSE83-A17715
Error Due to Nuclear Data Uncertainties in the Prediction of Large Liquid-Metal Fast Breeder Reactor Core Performance Parameters
Takanobu Kamei, Tadashi Yoshida
Nuclear Science and Engineering | Volume 84 | Number 2 | June 1983 | Pages 83-97
Technical Paper | doi.org/10.13182/NSE83-1
Neutron Capture Cross Sections of ¹⁸²W, ¹⁸³W, ¹⁸⁴W, and ¹⁸⁶W from 2.6 to 2000 keV
R. L. Macklin, D. M. Drake, E. D. Arthur
Nuclear Science and Engineering | Volume 84 | Number 2 | June 1983 | Pages 98-119
Technical Paper | doi.org/10.13182/NSE83-A17717
Model of the Deposition of Colloidal Crud Particles on the Fuel Elements of Nuclear Power Plants
Guillermo A. Urrutia, Susana I. Passaggio, A. J. G. Maroto, Miguel A. Blesa
Nuclear Science and Engineering | Volume 84 | Number 2 | June 1983 | Pages 120-130
Technical Paper | doi.org/10.13182/NSE83-A17718
Boiling and Dryout Behavior in a Liquid-Metal Fast Breeder Reactor Subassembly Bundle Under Low Heat Flux and Low Flow Conditions
M. Ishii, H. K. Fauske
Nuclear Science and Engineering | Volume 84 | Number 2 | June 1983 | Pages 131-146
Technical Paper | doi.org/10.13182/NSE83-A17719
On the Thermal Neutron Transport Processes in Liquid H₂O-D₂O Mixtures
R. M. Bansal, S. P. Tewari
Nuclear Science and Engineering | Volume 84 | Number 2 | June 1983 | Pages 147-150
Technical Note | doi.org/10.13182/NSE83-A17720
Higher Order Effects in Time-Dependent Sensitivity Problems
G. Palmiotti, M. Salvatores, J. C. Estiot, G. Granget
Nuclear Science and Engineering | Volume 84 | Number 2 | June 1983 | Pages 150-155
Technical Note | doi.org/10.13182/NSE83-A17721
Characterization of Neutron Leakage Probability, k_eff, and Critical Core Surface Mass Density of Small Reactor Assemblies Through the Trombay Criticality Formula
Anil Kumar, M. Srinivasan, K. Subba Rao
Nuclear Science and Engineering | Volume 84 | Number 2 | June 1983 | Pages 155-164
Technical Note | doi.org/10.13182/NSE83-A17722
New Approximations of Anisotropic Scattering in Neutron Transport and Diffusion Equations
T. Duracz, R. Zelazny
Nuclear Science and Engineering | Volume 84 | Number 2 | June 1983 | Pages 164-166
Technical Note | doi.org/10.13182/NSE83-A17723
A Drift-Flux Model Flow-Regime Map of Two-Phase Flows for Thermal-Hydraulic Calculations
S. Kaizerman, E. Wacholder, E. Elias
Nuclear Science and Engineering | Volume 84 | Number 2 | June 1983 | Pages 166-168
Technical Note | doi.org/10.13182/NSE83-A17724
Characteristics Analysis of Inhomogeneous, Nonequilibrium, Two-Phase Flows Using the Drift-Flux Model
S. Kaizerman, E. Wacholder, E. Elias
Nuclear Science and Engineering | Volume 84 | Number 2 | June 1983 | Pages 168-173
Technical Note | doi.org/10.13182/NSE83-A17725

Number 3

Table of Contents
CYLMAP (B. R. Wienke)
Installations nucléaires (Laurent Amyot)

An Unequal Velocity Model for Transient Two-Phase Flow by the Method of Characteristics
Dimitri Gidaspow, Firooz Rasouli, Yong W. Shin
Nuclear Science and Engineering | Volume 84 | Number 3 | July 1983 | Pages 179-195
Technical Paper | doi.org/10.13182/NSE83-A17788
Modeling Film Boiling Destabilization Due to a Pressure Shock Arrival
Michael L. Corradini
Nuclear Science and Engineering | Volume 84 | Number 3 | July 1983 | Pages 196-205
Technical Paper | doi.org/10.13182/NSE83-A17789
Generalized Perturbation Theory with Derivative Operators for Power Density Investigations in Nuclear Reactors
L. A. Belblidia, J. M. Kallfelz, D. G. Cacuci
Nuclear Science and Engineering | Volume 84 | Number 3 | July 1983 | Pages 206-225
Technical Paper | doi.org/10.13182/NSE83-A17790
Fast Neutron Spectra by Integral Experiments on Graphite with a Collimated Monoenergetic (D, T) Neutron Beam
A. Tsechanski, M. Segev, G. Shani
Nuclear Science and Engineering | Volume 84 | Number 3 | July 1983 | Pages 226-233
Technical Paper | doi.org/10.13182/NSE83-A17791
Neutron Capture Resonances in ⁵⁶Fe and ⁵⁸Fe in the Energy Range from 10 to 100 keV
F. Käppeler, K. Wisshak, L. D. Hong
Nuclear Science and Engineering | Volume 84 | Number 3 | July 1983 | Pages 234-247
Technical Paper | doi.org/10.13182/NSE83-A17792
Neutron Fission Cross Sections of ²³⁹Pu and ²⁴⁰Pu Relative to ²³⁵U
L. W. Weston, J. H. Todd
Nuclear Science and Engineering | Volume 84 | Number 3 | July 1983 | Pages 248-259
Technical Paper | doi.org/10.13182/NSE83-A17793
Streaming of 14-MeV Neutrons Through an Iron Duct—Comparison of Measured Neutron and Gamma-Ray Energy Spectra with Results Calculated Using the Monte Carlo MCNP Code
R. T. Santoro, J. M. Barnes, R. G. Alsmiller, Jr., P. D. Soran
Nuclear Science and Engineering | Volume 84 | Number 3 | July 1983 | Pages 260-270
Technical Paper | doi.org/10.13182/NSE83-A17794
Validity of the Monte Carlo Method for Shielding Analysis of a Spent-Fuel Shipping Cask: Comparison with Experiment
K. Ueki, M. Inoue, Y. Maki
Nuclear Science and Engineering | Volume 84 | Number 3 | July 1983 | Pages 271-284
Technical Paper | doi.org/10.13182/NSE83-A17795
Particle Transport Theory in a Finite Sphere Containing a Spherical-Shell Source
C. E. Siewert, J. R. Thomas, Jr.
Nuclear Science and Engineering | Volume 84 | Number 3 | July 1983 | Pages 285-290
Technical Paper | doi.org/10.13182/NSE84-285
Plutonium Diffusion in Advanced Fuels (U,Pu)(C,O) and (U,Pu)(C,N)
M. H. Bradbury, Hj. Matzke
Nuclear Science and Engineering | Volume 84 | Number 3 | July 1983 | Pages 291-293
Technical Note | doi.org/10.13182/NSE83-A17797
Additional Remarks on BeH₂ as a Moderator in Minimum Critical Mass Systems
P. K. Job, K. Subba Rao, M. Srinivasan
Nuclear Science and Engineering | Volume 84 | Number 3 | July 1983 | Pages 293-298
Technical Note | doi.org/10.13182/NSE83-A17798
Reduction of “Calculational” Uncertainties Due to Approximate Fission-Source Matrices
U. Salmi, J. J. Wagschal, A. Yaari, Y. Yeivin
Nuclear Science and Engineering | Volume 84 | Number 3 | July 1983 | Pages 298-300
Technical Note | doi.org/10.13182/NSE83-A17799
Monte Carlo Calculations of a Fusion Reactor Shielding Experiment
Eldon Schmidt, Philip F. Rose
Nuclear Science and Engineering | Volume 84 | Number 3 | July 1983 | Pages 300-304
Technical Note | doi.org/10.13182/NSE83-A17800

Number 4

Table of Contents
Fast Breeder Reactors (Neil Todreas, Michael Driscoll)

Boundary Perturbation Theory for Inhomogeneous Transport Equations
F. Rahnema, G. C. Pomraning
Nuclear Science and Engineering | Volume 84 | Number 4 | August 1983 | Pages 313-319
Technical Paper | doi.org/10.13182/NSE83-A15451
The Radioactive Decay of ^44gSc and ^44mSc
Guanjun Yuan, Shiping Chen, Benhua Han, Ling Zhou, Peikun Weng
Nuclear Science and Engineering | Volume 84 | Number 4 | August 1983 | Pages 320-323
Technical Paper | doi.org/10.13182/NSE83-A15452
Lumped Fission Product Neutron Cross Sections Based on ENDF/B-V for Fast Reactor Analysis
J. R. Liaw, H. Henryson II
Nuclear Science and Engineering | Volume 84 | Number 4 | August 1983 | Pages 324-336
Technical Paper | doi.org/10.13182/NSE83-A15453
Neutron Streaming Through a Slit and Duct in Concrete Shields and Comparison with a Monte Carlo Analysis
Hiroyuki Hashikura, Hideshi Fukumoto, Yoshiaki Oka, Masatsugu Akiyama, Shigehiro An
Nuclear Science and Engineering | Volume 84 | Number 4 | August 1983 | Pages 337-344
Technical Paper | doi.org/10.13182/NSE83-A15454
Acoustic Mismatch Theory for Heat Flow Across Fuel-Cladding Interfaces in Fast Reactors
G. Dharmadurai
Nuclear Science and Engineering | Volume 84 | Number 4 | August 1983 | Pages 345-349
Technical Paper | doi.org/10.13182/NSE83-A15455
Two-Dimensional Numerical Modeling of Nonisothermal Flows for Unsteady Thermal-Hydraulic Analysis
P. L. Viollet, J. P. Benque, J. Goussebaile
Nuclear Science and Engineering | Volume 84 | Number 4 | August 1983 | Pages 350-372
Technical Paper | doi.org/10.13182/NSE83-A15456
Pattern Recognition Techniques Applied to Acoustic Detection of Liquid-Metal Fast Breeder Reactor Cooling Defects
M. Brunet, B. Dubuisson
Nuclear Science and Engineering | Volume 84 | Number 4 | August 1983 | Pages 373-379
Technical Paper | doi.org/10.13182/NSE83-A15457
Relation Between Koebke's Equivalence Theory and Benoist's Cell Homogenization Procedure
S. V. G. Menon, D. C. Sahni
Nuclear Science and Engineering | Volume 84 | Number 4 | August 1983 | Pages 380-383
Technical Note | doi.org/10.13182/NSE83-A15458
An Interpolation Method for the Transport Theory and Its Application in Fusion Neutronics Analysis
Jungchung Jung
Nuclear Science and Engineering | Volume 84 | Number 4 | August 1983 | Pages 383-388
Technical Note | doi.org/10.13182/NSE83-A15459
On Zero Variance Monte Carlo Path-Stretching Schemes
Iván Lux
Nuclear Science and Engineering | Volume 84 | Number 4 | August 1983 | Pages 388-390
Technical Note | doi.org/10.13182/NSE83-A15460
A Fast Nodal Neutron Diffusion Method for Cartesian Geometry
Mihály Makai, Claude Maeder
Nuclear Science and Engineering | Volume 84 | Number 4 | August 1983 | Pages 390-395
Technical Note | doi.org/10.13182/NSE83-A15461
Gamma-Ray Production Due to Neutron Interactions with Copper for Neutron Energies Between 0.7 and 10.5 MeV
G. G. Slaughter, J. K. Dickens
Nuclear Science and Engineering | Volume 84 | Number 4 | August 1983 | Pages 395-406
Technical Note | doi.org/10.13182/NSE83-A15462