Home / Publications / Journals / Nuclear Science and Engineering / Volume 92

Volume 92

Number 1 | Number 2 | Number 3 | Number 4

Number 1

Table of Contents
Advances in Nuclear Engineering Computational Methods(R. M. Westfall)

Vectorization of Transport and Diffusion Computations on the CDC Cyber 205

I. K. Abu-Shumays

Nuclear Science and Engineering / Volume 92 / Number 1 / January 1986 / Pages 4-19

Technical Paper / dx.doi.org/10.13182/NSE86-A17859

Experience with the Incomplete Cholesky Conjugate Gradient Method in a Diffusion Code

Willi Hoebel

Nuclear Science and Engineering / Volume 92 / Number 1 / January 1986 / Pages 20-26

Technical Paper / dx.doi.org/10.13182/NSE86-A17860

Performance of a Nonstationary Implicit Scheme for Solving Large Systems of Linear Equations

J. M. Barry, J. P. Pollard

Nuclear Science and Engineering / Volume 92 / Number 1 / January 1986 / Pages 27-33

Technical Paper / dx.doi.org/10.13182/NSE86-A17861

Perturbation Theory Based on a Nodal Model

Temitope A. Taiwo, A. F. Henry

Nuclear Science and Engineering / Volume 92 / Number 1 / January 1986 / Pages 34-41

Technical Paper / dx.doi.org/10.13182/NSE86-A17862

Numerical Solution of Neutron Diffusion Equations in Multiconnected Regions Using Compound Boundary-Fitted Coordinate Systems

Motoo Aoyama and Sadao Uchikawa

Nuclear Science and Engineering / Volume 92 / Number 1 / January 1986 / Pages 42-50

Technical Paper / dx.doi.org/10.13182/NSE86-A17863

Diffusion Coefficient in Nonuniform Lattices

A. Dévényi, J. Gadó, A. Keresztúri, M. Makai

Nuclear Science and Engineering / Volume 92 / Number 1 / January 1986 / Pages 51-55

Technical Paper / dx.doi.org/10.13182/NSE86-A17864

Application and Verification of the Simplified Equivalence Theory for Burnup States

K. Koebke, H. Haase, L. Hetzelt, H.-J. Winter

Nuclear Science and Engineering / Volume 92 / Number 1 / January 1986 / Pages 56-65

Technical Paper / dx.doi.org/10.13182/NSE86-A17865

Use of a Dynamic Grid Adaptation in the Asymmetric Weighted Residual Method

U. Graf, P. Romstedt, W. Werner

Nuclear Science and Engineering / Volume 92 / Number 1 / January 1986 / Pages 66-70

Technical Paper / dx.doi.org/10.13182/NSE86-A17866

Numerical Analysis of Critical Two-Phase Flow in a Convergent-Divergent Nozzle

P. Romstedt, W. Werner

Nuclear Science and Engineering / Volume 92 / Number 1 / January 1986 / Pages 71-83

Technical Paper / dx.doi.org/10.13182/NSE86-A17867

Finite Element Solution of the Fokker-Plonck Equation in Electrostatic Magnetic Mirror Fusion Machines

Taha H. Zerguini

Nuclear Science and Engineering / Volume 92 / Number 1 / January 1986 / Pages 84-91

Technical Paper / dx.doi.org/10.13182/NSE86-A17868

A One-Dimensional Hybrid Code for Field-Reversed Mirror Dynamics

R. A. Stark, G. H. Miley

Nuclear Science and Engineering / Volume 92 / Number 1 / January 1986 / Pages 92-97

Technical Paper / dx.doi.org/10.13182/NSE86-A17869

A Linear Discontinuous Galerkin Approximation for the Continuous Slowing Down Operator

Maximo S. Lazo, J. E. Morel

Nuclear Science and Engineering / Volume 92 / Number 1 / January 1986 / Pages 98-109

Technical Paper / dx.doi.org/10.13182/NSE86-A17870

Electron Transport Calculational Methods for a Plane Source Embedded in an Infinite Medium

S. Woolf, W. L. Filippone, B. D. Ganapol, J. C. Garth

Nuclear Science and Engineering / Volume 92 / Number 1 / January 1986 / Pages 110-118

Technical Paper / dx.doi.org/10.13182/NSE86-A17871

Semi-Implicit Method for Three-Dimensional Resistive Magnetohydrodynamic Simulation of Fusion Plasmas

Douglas S. Harned, W. Kerner

Nuclear Science and Engineering / Volume 92 / Number 1 / January 1986 / Pages 119-125

Technical Paper / dx.doi.org/10.13182/NSE86-A17872

Vectorization of the Light Water Reactor Transient Analysis Code RELAP5

Misako Ishiguro and Hiroo Harada, Naohisa Shinozawa and Ken-itsu Naraoka

Nuclear Science and Engineering / Volume 92 / Number 1 / January 1986 / Pages 126-135

Technical Paper / dx.doi.org/10.13182/NSE86-A17873

Numerical Experiments in Concurrent Multiprocessing with the RELAP5 Nuclear Reactor Systems Code

H. Makowitz

Nuclear Science and Engineering / Volume 92 / Number 1 / January 1986 / Pages 136-143

Technical Paper / dx.doi.org/10.13182/NSE86-A17874

Boiling Water Reactor Plant Analyzer Development at Brookhaven National Laboratory

H. S. Cheng, W. Wulff, A. N. Mallen, S. V. Lekach, A. Stritar, R. J. Cerbone

Nuclear Science and Engineering / Volume 92 / Number 1 / January 1986 / Pages 144-156

Technical Paper / dx.doi.org/10.13182/NSE86-A17875

Solution of Large Unsymmetric Eigensystems for Fluid/Structure Interaction Problems

I.-W. Yu

Nuclear Science and Engineering / Volume 92 / Number 1 / January 1986 / Pages 157-161

Technical Paper / dx.doi.org/10.13182/NSE86-A17876

A Method of Computing Hydraulic Reaction Force Due to a Fluid Jet at a Steamline Break

S. Abedin, K. Takeuchi, M. Y. Young

Nuclear Science and Engineering / Volume 92 / Number 1 / January 1986 / Pages 162-169

Technical Paper / dx.doi.org/10.13182/NSE86-A17877

An Advanced Multidimensional Method for Structural and Hydrodynamic Analysis of Liquid-Metal Fast Breeder Reactor Piping Systems

C. Y. Wang, W. R. Zeuch

Nuclear Science and Engineering / Volume 92 / Number 1 / January 1986 / Pages 170-177

Technical Paper / dx.doi.org/10.13182/NSE86-A17878

Number 2

Table of Contents
The Integrated TIGER Series (ITS) of Coupled Electron/Photon Monte Carlo Transport Codes(J. A. Halbleib and T. A. Mehlhorn)
Temps(B. D. Ganapol)

Projected Discrete Ordinates Methods for Numerical Transport Problems

Edward W. Larsen

Nuclear Science and Engineering / Volume 92 / Number 2 / February 1986 / Pages 179-185

Technical Paper / dx.doi.org/10.13182/NSE86-A18163

Nonlinear Diffusion Synthetic Acceleration Difference Schemes for Radiative Transfer Applications

Bradley A. Clark

Nuclear Science and Engineering / Volume 92 / Number 2 / February 1986 / Pages 186-191

Technical Paper / dx.doi.org/10.13182/NSE86-A18164

Augmented Weighted-Diamond Form of the Linear-Nodal Scheme for Cartesian Coordinate Systems

Wallace F. Walters

Nuclear Science and Engineering / Volume 92 / Number 2 / February 1986 / Pages 192-196

Technical Paper / dx.doi.org/10.13182/NSE86-A18165

Discontinuous Finite Element Method for Solving the Two-Dimesional Neutron Transport Equation on Lagrangian Meshes

G. Samba

Nuclear Science and Engineering / Volume 92 / Number 2 / February 1986 / Pages 197-203

Technical Paper / dx.doi.org/10.13182/NSE86-A18166

Finite Element Formulations of Nodal Schemes for Neutron Diffusion and Transport Problems

E. Del Valle, J. P. Hennart, D. Meade

Nuclear Science and Engineering / Volume 92 / Number 2 / February 1986 / Pages 204-211

Technical Paper / dx.doi.org/10.13182/NSE86-A18167

The DC_N-S_N Hybrid Method for Neutron Transport Calculations in (r-z) Geometry

Yoichi Watanabe and Charles W. Maynard

Nuclear Science and Engineering / Volume 92 / Number 2 / February 1986 / Pages 212-217

Technical Paper / dx.doi.org/10.13182/NSE86-A18168

Linear Discontinuous Finite Elements for Phase-Space Multidimensional Transport Calculations

M. Mordant

Nuclear Science and Engineering / Volume 92 / Number 2 / February 1986 / Pages 218-227

Technical Paper / dx.doi.org/10.13182/NSE86-A18169

Use of Multidimensional Transport Methodology on Nuclear Logging Problems

John J. Ullo

Nuclear Science and Engineering / Volume 92 / Number 2 / February 1986 / Pages 228-239

Technical Paper / dx.doi.org/10.13182/NSE86-A18170

Interface Current Method for Cluster Geometry

G. Marleau, A. Hébert

Nuclear Science and Engineering / Volume 92 / Number 2 / February 1986 / Pages 240-246

Technical Paper / dx.doi.org/10.13182/NSE86-A18171

A Transport Multicell Method for Two-Dimensional Lattices of Hexagonal Cells

Richard Sanchez

Nuclear Science and Engineering / Volume 92 / Number 2 / February 1986 / Pages 247-254

Technical Paper / dx.doi.org/10.13182/NSE86-A18172

Refinement of the Substructure Method for Integral Transport Calculations

Žarko Stankovski

Nuclear Science and Engineering / Volume 92 / Number 2 / February 1986 / Pages 255-260

Technical Paper / dx.doi.org/10.13182/NSE86-A18173

A Generalization of the Livolant-Jeanpierre Theory for Resonance Absorption Calculation

P. Reuss

Nuclear Science and Engineering / Volume 92 / Number 2 / February 1986 / Pages 261-266

Technical Paper / dx.doi.org/10.13182/NSE86-A18174

Internal Interface Perturbations: Calculational Method Using the Eigenvalue Innplicit Expansion of the Conditioned Problem

J. Porta, J. Y. Doriath, B. Martinet

Nuclear Science and Engineering / Volume 92 / Number 2 / February 1986 / Pages 267-271

Technical Paper / dx.doi.org/10.13182/NSE86-A18175

Solution of the One-Group Time-Dependent Neutron Transport Equation in an Infinite Medium by Polynomial Reconstruction

B. D. Ganapol

Nuclear Science and Engineering / Volume 92 / Number 2 / February 1986 / Pages 272-279

Technical Paper / dx.doi.org/10.13182/NSE86-A18176

Monte Carlo Techniques for Analyzing Deep-Penetration Problems

S. N. Cramer, J. Gonnord, J. S. Hendricks

Nuclear Science and Engineering / Volume 92 / Number 2 / February 1986 / Pages 280-288

Technical Paper / dx.doi.org/10.13182/NSE86-A18177

Review of Monte Carlo Techniques for Analyzing Reactor Perturbations

H. Rief, E. M. Gelbard, R. W. Schaefer, K. S. Smith

Nuclear Science and Engineering / Volume 92 / Number 2 / February 1986 / Pages 289-297

Technical Paper / dx.doi.org/10.13182/NSE86-A18178

Vectorization of the KENO-IV Code

Kiyoshi Asai, Kenji Higuchi, and Jun-ichi Katakura, Yutaka Kurita

Nuclear Science and Engineering / Volume 92 / Number 2 / February 1986 / Pages 298-307

Technical Paper / dx.doi.org/10.13182/NSE86-A18179

Thermal-Hydraulic Methods in Fast Reactor Safety

David P. Weber and Laural L. Briggs

Nuclear Science and Engineering / Volume 92 / Number 2 / February 1986 / Pages 308-329

Technical Paper / dx.doi.org/10.13182/NSE86-A18180

On Trial Functions in the Nested Element Method

D. V. Altiparmakov

Nuclear Science and Engineering / Volume 92 / Number 2 / February 1986 / Pages 330-337

Technical Paper / dx.doi.org/10.13182/NSE86-A18181

Number 3

Table of Contents
Comments on the “Weinberg” Issue(Dixon Callihan)
An Additional Comment on the “Weinberg” Issue(Arthur H. Snell)
Comments on the Richardson Extrapolation(S. M. Lee)
Reply to “Comments on Richardson Extrapolation”(Mihály Makai)

On the Solution of the Inverse Problem of Radiation Scattering Imaging

E. M. A. Hussein, D. A. Meneley, S. Banerjee

Nuclear Science and Engineering / Volume 92 / Number 3 / March 1986 / Pages 341-349

Technical Paper / dx.doi.org/10.13182/NSE86-A17524

Fast Neutron Inelastic Scattering Cross Sections of ²³⁸U for States Between 680 and 1530 keV

J. Q. Shao, G. P. Couchell, J. J. Egan, G. H. R. Kegel, S. Q. Li, A. Mittler, D. J. Pullen, W. A. Schier, E. D. Arthur

Nuclear Science and Engineering / Volume 92 / Number 3 / March 1986 / Pages 350-371

Technical Paper / dx.doi.org/10.13182/NSE86-A17525

A Three-Dimensional Neutronics Model for Reactor Training Simulators

M. V. Gregory, B. N. Aviles, S. J. Yakura

Nuclear Science and Engineering / Volume 92 / Number 3 / March 1986 / Pages 372-381

Technical Paper / dx.doi.org/10.13182/NSE86-A17526

The Transport of 14-MeV Neutrons Through Heavy Materials 150 < A < 208

L. F. Hansen, H. M. Blann, R. J. Howerton, T. T. Komoto, B. Pohl

Nuclear Science and Engineering / Volume 92 / Number 3 / March 1986 / Pages 382-396

Technical Paper / dx.doi.org/10.13182/NSE86-A17527

Spherical Harmonics Method for a Two-Dimensional Multigroup Transport Equation Using a Semi-Discrete Ordinates Equation: Part I

Keisuke Kobayashi

Nuclear Science and Engineering / Volume 92 / Number 3 / March 1986 / Pages 397-406

Technical Paper / dx.doi.org/10.13182/NSE86-A17528

Spherical Harmonics Method for a Two-Dimensional Multigroup Transport Equation Using a Semi-Discrete Ordinates Equation: Part II

Keisuke Kobayashi and Tsuyoshi Misawa

Nuclear Science and Engineering / Volume 92 / Number 3 / March 1986 / Pages 407-420

Technical Paper / dx.doi.org/10.13182/NSE86-A17529

Analytic Solution of the Spencer-Lewis Angular-Spatial Moments Equations

W. L. Filippone

Nuclear Science and Engineering / Volume 92 / Number 3 / March 1986 / Pages 421-439

Technical Paper / dx.doi.org/10.13182/NSE86-A17530

Simplified Spin Cutoff Factors for Particle-Hole Level Densities in Precompound Nuclear Reaction Theory

C. Y. Fu

Nuclear Science and Engineering / Volume 92 / Number 3 / March 1986 / Pages 440-453

Technical Paper / dx.doi.org/10.13182/NSE86-A17531

Construction of Adjoint Operators for Coupled Equations Depending on Different Variables

J. E. Hoogenboom

Nuclear Science and Engineering / Volume 92 / Number 3 / March 1986 / Pages 454-458

Technical Note / dx.doi.org/10.13182/NSE86-A17532

The Inelastic Scattering of Neutrons by ²³²Th

A.M. Street, P.E. Hodgson

Nuclear Science and Engineering / Volume 92 / Number 3 / March 1986 / Pages 459-464

Technical Note / dx.doi.org/10.13182/NSE86-A17533

A Monte Carlo Learning/Biasing Experiment with Intelligent Random Numbers

Thomas E. Booth

Nuclear Science and Engineering / Volume 92 / Number 3 / March 1986 / Pages 465-481

Technical Note / dx.doi.org/10.13182/NSE86-A17534

Analytical Results of Variance Reduction Characteristics of Biased Monte Carlo for Deep-Penetration Problems

K. P. N. Murthy, R. Indira

Nuclear Science and Engineering / Volume 92 / Number 3 / March 1986 / Pages 482-487

Technical Note / dx.doi.org/10.13182/NSE86-A17535

Number 4

Table of Contents
On the Discrete Ordinates Method in Spherical Geometry(R. S. Modak)
On Efficient Estimation of Variances(Ivan Lux)
Limitations on the Use of the THOR Critical Assembly for Validation of n + 239Pu Cross Sections(R. S. Keshavamurthy, S. Ganesan)
Response to "Limitations on the Use of the THOR Critical Assembly for Validation of n + 239Pu Cross Sections"(E. D. Arthur, P. G. Young, D. G. Mad/and, R. E. MacFarlane)

Helium Production in Pure Elements, Isotopes, and Alloy Steels by 14.8-MeV Neutrons

D. W. Kneff, B. M. Oliver., Harry Farrar IV, L. R. Greenwood

Nuclear Science and Engineering / Volume 92 / Number 4 / April 1986 / Pages 491-524

Technical Paper / dx.doi.org/10.13182/NSE86-A18608

Neutron Transmission Measurement and Resonance Analysis of 93Zr from 60 to 6000 eV

R. L. Macklin, J. A. Harvey, N. W. Hill

Nuclear Science and Engineering / Volume 92 / Number 4 / April 1986 / Pages 525-530

Technical Paper / dx.doi.org/10.13182/NSE86-A18609

Optimal Control of a Boiling Water Reactor in Load-Following via Multilevel Methods

Chaung Lin,Lawrence M. Grossman

Nuclear Science and Engineering / Volume 92 / Number 4 / April 1986 / Pages 531-544

Technical Paper / dx.doi.org/10.13182/NSE86-A18610

Biasing Parameter Limits for Synergistic Monte Carlo in Deep-Penetration Calculations

S. R. Dwivedi, H. C. Gupta

Nuclear Science and Engineering / Volume 92 / Number 4 / April 1986 / Pages 545-549

Technical Paper / dx.doi.org/10.13182/NSE86-A18611

Two-Parametric Presentation of Thermal Neutron Flux in Infinite Hydrogenous Media

D. Ingman, E. Taviv

Nuclear Science and Engineering / Volume 92 / Number 4 / April 1986 / Pages 550-569

Technical Paper / dx.doi.org/10.13182/NSE86-A18612

Radiation Transfer in a Cylindrical Vessel Containing High-Temperature Corium Aerosols

M. P. Mengüç, R. Viskanta

Nuclear Science and Engineering / Volume 92 / Number 4 / April 1986 / Pages 570-583

Technical Paper / dx.doi.org/10.13182/NSE86-A18613

Monte Carlo and Discrete Ordinates Calculations of 14-MeV Neutrons Streaming Through a Stainless Steel Duct: Comparison with Experiment I

R. T. Santoro, J. M. Barnes,R. G. Alsmiller, Jr.,J. D. Drischler

Nuclear Science and Engineering / Volume 92 / Number 4 / April 1986 / Pages 584-595

Technical Notes / dx.doi.org/10.13182/NSE86-A18614

Gamma-Ray Energy Deposition Measurements in the Fast Breeder Blanket Facility

K. R. Koch, F. M. Clikeman,R. H. Johnson

Nuclear Science and Engineering / Volume 92 / Number 4 / April 1986 / Pages 596-605

Technical Notes / dx.doi.org/10.13182/NSE86-A18615