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Volume 84

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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)
Comments on “The Effects of Intracell Adjoint Flux Heterogeneity on First-Order Perturbation Reactivity Calculations”(Ehud Greenspan)
Response to “Comments on ‘The Effects of Intracell Adjoint Flux Heterogeneity on First-Order Perturbation Reactivity Calculations’”(Kord S. Smith)

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NSE83-A15462