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Volume 65

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Number 1

Table of Contents
Fusion Reactor Physics: Principles and Technology(Robert A. Gross)
Determination of Uranium and Plutonium in Nuclear Fuels(Werner Müller)
Introduction to Experimental Nuclear Physics(M. A. Schultz)
The Chemistry of Americium(M. H. Lloyd)
Comments on Particle Transport in Finite Rods(Raphael Aronson)
Comments on Beryllium (n, 2n) Cross Sections in ENDF/B-IV and -V(R. J. Howerton, S. T. Perkins)

A Multivariable Autoregressive Model of the Dynamics of a Boiling Water Reactor

K. Matsubara, R. Oguma, M. Kitamura

Nuclear Science and Engineering / Volume 65 / Number 1 / January 1978 / Pages 1-16

Technical Paper / dx.doi.org/10.13182/NSE78-A27121

Void Distribution in Boiling Pools with Internal Heat Generation

Mujid S. Kazimi, John C. Chen

Nuclear Science and Engineering / Volume 65 / Number 1 / January 1978 / Pages 17-27

Technical Paper / dx.doi.org/10.13182/NSE78-A27122

Pinhole Imaging of a Test Fuel Element at the Transient Reactor Test Facility

George J. Berzins, Ki S. Han

Nuclear Science and Engineering / Volume 65 / Number 1 / January 1978 / Pages 28-40

Technical Paper / dx.doi.org/10.13182/NSE78-A27123

Critical Experiments Measuring the Reactivity Worths of Materials Commonly Encountered as Fixed Neutron Absorbers

S. R. Bierman, B. M. Durst, E. D. Clayton

Nuclear Science and Engineering / Volume 65 / Number 1 / January 1978 / Pages 41-48

Technical Paper / dx.doi.org/10.13182/NSE78-A27124

Cross Sections for Gamma-Ray Production by 1A-MeV Neutrons

D. M. Drake, E. D. Arthur, M. G. Silbert

Nuclear Science and Engineering / Volume 65 / Number 1 / January 1978 / Pages 49-64

Technical Paper / dx.doi.org/10.13182/NSE78-A27125

Differential Elastic Scattering Cross Sections of Boron-10 for Neutrons of 4 to 8 MeV Energy

H. D. Knox, R. M. White, R. O. Lane

Nuclear Science and Engineering / Volume 65 / Number 1 / January 1978 / Pages 65-69

Technical Paper / dx.doi.org/10.13182/NSE78-A27126

The Differential Neutron Scattering Cross Sections of Uranium-238 at 144 keV

Francis Y. Tsang, Robert M. Brugger

Nuclear Science and Engineering / Volume 65 / Number 1 / January 1978 / Pages 70-75

Technical Paper / dx.doi.org/10.13182/NSE78-A27127

Neutron Resonance Spectroscopy in Vanadium, Manganese, and Cobalt

J. B. Garg

Nuclear Science and Engineering / Volume 65 / Number 1 / January 1978 / Pages 76-92

Technical Paper / dx.doi.org/10.13182/NSE78-A27128

A New Monte Carlo Approach to the Adjoint Boltzmann Equation

Artenio De Matteis, Rolando Simonini

Nuclear Science and Engineering / Volume 65 / Number 1 / January 1978 / Pages 93-105

Technical Paper / dx.doi.org/10.13182/NSE78-A27129

Space-Time Dynamics of a Fast Breeder Reactor for Localized Disturbances

Jagdeep B. Doshi, Lawrence M. Grossman

Nuclear Science and Engineering / Volume 65 / Number 1 / January 1978 / Pages 106-129

Technical Paper / dx.doi.org/10.13182/NSE78-A27130

A Computational Method for Neutron Transport Problems in Toroidal Geometry

Jungchung Jung

Nuclear Science and Engineering / Volume 65 / Number 1 / January 1978 / Pages 130-140

Technical Paper / dx.doi.org/10.13182/NSE78-A27131

Radiation Behavior of Vitreous Silica

William Primak

Nuclear Science and Engineering / Volume 65 / Number 1 / January 1978 / Pages 141-145

Technical Note / dx.doi.org/10.13182/NSE78-A27132

Two-Dimensional Void Reconstruction by Neutron Transmission

G. D. Zakaib, A. A. Harms, J. Vlachopoulos

Nuclear Science and Engineering / Volume 65 / Number 1 / January 1978 / Pages 145-154

Technical Note / dx.doi.org/10.13182/NSE78-A27133

Experimental Investigation of Neutrons Streaming Through the Grid-Plate Shield of Liquid-Metal Fast Breeder Reactors

Shunsuke Uchida, Masao Kitamura, Shunichi Miyasaka

Nuclear Science and Engineering / Volume 65 / Number 1 / January 1978 / Pages 155-159

Technical Note / dx.doi.org/10.13182/NSE78-A27134

Measurement of the Neutron Spectrum from a Fast Pulse Reactor in the Presence of the Experimenter's Table

J. T. Harvey, J. L. Meason, H. L. Wright

Nuclear Science and Engineering / Volume 65 / Number 1 / January 1978 / Pages 160-161

Technical Note / dx.doi.org/10.13182/NSE78-A27135

On the Spherical Harmonics Treatment of Epithermal-Neutron Spectra in Reactor Lattices—Further Developments and Improvements

M. V. Mataušek

Nuclear Science and Engineering / Volume 65 / Number 1 / January 1978 / Pages 161-164

Technical Note / dx.doi.org/10.13182/NSE78-A27136

Fast-Neutron Cross Sections for Curium-244

Horacio Fernández Gianotti

Nuclear Science and Engineering / Volume 65 / Number 1 / January 1978 / Pages 164-166

Technical Note / dx.doi.org/10.13182/NSE78-A27137

Fission Cross Section for Curium-245 from 0.01 to 35 eV

J. C. Browne, R. W. Benjamin, D. G. Karraker

Nuclear Science and Engineering / Volume 65 / Number 1 / January 1978 / Pages 166-170

Technical Note / dx.doi.org/10.13182/NSE78-A27138

The Fission Cross Sections of Uranium-234 and Uranium-236 Relative to Uranium-235

J. W. Meadows

Nuclear Science and Engineering / Volume 65 / Number 1 / January 1978 / Pages 171-174

Technical Note / dx.doi.org/10.13182/NSE78-2

Neutron Scattering and the Optical Model near A = 208 and Implications on the Inelastic Scattering Cross Section of Uranium-238

P. T. Guenther, D. G. Havel, A. B. Smith

Nuclear Science and Engineering / Volume 65 / Number 1 / January 1978 / Pages 174-180

Technical Note / dx.doi.org/10.13182/NSE78-A27140

Neutron Diffusion Across an Absorption Discontinuity in Water Assemblies

S. K. Trikha, S. C. Jain

Nuclear Science and Engineering / Volume 65 / Number 1 / January 1978 / Pages 180-182

Technical Note / dx.doi.org/10.13182/NSE78-A27141

Tailoring the Breeding-Fission Ratio in a Hybrid Fusion Reactor Blanket by Neutron Moderation with Iron

Gad Shani

Nuclear Science and Engineering / Volume 65 / Number 1 / January 1978 / Pages 183-187

Technical Note / dx.doi.org/10.13182/NSE78-A27142

Sensitivity Theory for General Nonlinear Algebraic Equations with Constraints

E. M. Oblow

Nuclear Science and Engineering / Volume 65 / Number 1 / January 1978 / Pages 187-191

Technical Note / dx.doi.org/10.13182/NSE78-A27143

On Multiregion Problems in Plane Geometry and the Use of Half-Range Orthogonality Relations

Yuji Ishiguro

Nuclear Science and Engineering / Volume 65 / Number 1 / January 1978 / Pages 191-196

Technical Note / dx.doi.org/10.13182/NSE78-A27144

Number 2

Table of Contents
Sensitivity Theory from a Differential Viewpoint(E. M. Oblow)

The C_N Method of Solving the Transport Equation: Application to Plane Geometry

Alain Kavenoky

Nuclear Science and Engineering / Volume 65 / Number 2 / February 1978 / Pages 209-225

Technical Paper / dx.doi.org/10.13182/NSE78-A27152

Generalized Rebalance: A Common Framework for Transport Acceleration Methods

W. F. Miller, Jr.

Nuclear Science and Engineering / Volume 65 / Number 2 / February 1978 / Pages 226-236

Technical Paper / dx.doi.org/10.13182/NSE78-A27153

Application of the Fictitious Scattering Radiation Transport Model for Deep-Penetration Monte Carlo Calculations

S. N. Cramer

Nuclear Science and Engineering / Volume 65 / Number 2 / February 1978 / Pages 237-253

Technical Paper / dx.doi.org/10.13182/NSE78-A27154

Multidimensional Space-Time Nuclear Reactor Kinetics Studies. Part III: Three-Dimensional Experiments

W. G. Winn, P. B. Parks, N. P. Baumann, C. E. Jewell

Nuclear Science and Engineering / Volume 65 / Number 2 / February 1978 / Pages 254-272

Technical Paper / dx.doi.org/10.13182/NSE78-A27155

Prediction of Monte Carlo Errors by a Theory Generalized to Treat Track-Length Estimators

Thomas E. Booth, Harvey J. Amster

Nuclear Science and Engineering / Volume 65 / Number 2 / February 1978 / Pages 273-281

Technical Paper / dx.doi.org/10.13182/NSE78-A27156

Critical Impurity Concentrations for Power Multiplication in Beam-Heated Toroidal Fusion Reactors

R. V. Jensen, D. E. Post, D. L. Jassby

Nuclear Science and Engineering / Volume 65 / Number 2 / February 1978 / Pages 282-289

Technical Paper / dx.doi.org/10.13182/NSE78-A27157

Neutron Drift in Heterogeneous Media

Edward W. Larsen, Michael Williams

Nuclear Science and Engineering / Volume 65 / Number 2 / February 1978 / Pages 290-302

Technical Paper / dx.doi.org/10.13182/NSE78-A27158

Calculation of Neutron and Gamma-Ray Energy Spectra in Liquid Air and Liquid Nitrogen Due to 14-MeV Neutron and Californium-252 Sources

E. A. Straker, M. L. Gritzner, L. Harris, Jr.

Nuclear Science and Engineering / Volume 65 / Number 2 / February 1978 / Pages 303-315

Technical Paper / dx.doi.org/10.13182/NSE78-A27159

Threshold-Foil Measurements of Reactor Neutron Spectra for Radiation Damage Applications

Victor V. Verbinski, Norman A. Lurie, Vern C. Rogers

Nuclear Science and Engineering / Volume 65 / Number 2 / February 1978 / Pages 316-330

Technical Paper / dx.doi.org/10.13182/NSE78-A27160

Measurement of the Differential Elastic and Inelastic Neutron Scattering Cross Sections of Carbon from 8.0 to 14.5 MeV

G. Haouat, J. Lachkar, J. Sigaud, Y. Patin, F. Coçu

Nuclear Science and Engineering / Volume 65 / Number 2 / February 1978 / Pages 331-346

Technical Paper / dx.doi.org/10.13182/NSE78-A27161

Neutron Total Cross-Section Measurement of Thorium Near 24 keV with an Iron-Filtered Neutron Beam

Katsuhei Kobayashi, Yoshiaki Fujita, Tohru Oosaki, Robert C. Block

Nuclear Science and Engineering / Volume 65 / Number 2 / February 1978 / Pages 347-353

Technical Paper / dx.doi.org/10.13182/NSE78-A27162

Use of Interactive Graphic Techniques to Evaluate Uranium-238 Cross Sections from Integral Measurements

Ansar Parvez, Martin Becker

Nuclear Science and Engineering / Volume 65 / Number 2 / February 1978 / Pages 354-367

Technical Paper / dx.doi.org/10.13182/NSE78-A27163

Application of Nuclear Reaction Models for Neutron Nuclear Data Evaluation: Statistical and Optical Model Calculations for ^134–138Ba

B. Strohmaier, M. Uhl, W. K. Matthes

Nuclear Science and Engineering / Volume 65 / Number 2 / February 1978 / Pages 368-384

Technical Paper / dx.doi.org/10.13182/NSE78-A27164

A Digital Transfer Matrix for Fuel Pin Heat Transfer

Michael D. Green, Jak Kornfilt

Nuclear Science and Engineering / Volume 65 / Number 2 / February 1978 / Pages 385-393

Technical Paper / dx.doi.org/10.13182/NSE78-A27165

Experimental Studies of the Growth of an Internally Heated Liquid Pool in a Solid Bed

Rouyentan Farhadieh, Louis Baker, Jr.

Nuclear Science and Engineering / Volume 65 / Number 2 / February 1978 / Pages 394-400

Technical Paper / dx.doi.org/10.13182/NSE78-A27166

Probabilistic Analysis of Liquid-Metal Fast Breeder Reactor Accident Consequences with Response Surface Techniques

J. K. Vaurio, C. Mueller

Nuclear Science and Engineering / Volume 65 / Number 2 / February 1978 / Pages 401-413

Technical Paper / dx.doi.org/10.13182/NSE78-A27167

Approximation to cosγ Appearing in the Formula for the Coulomb Scattering of Relativistic Electrons

Tatsuo Tabata, Rinsuke Ito

Nuclear Science and Engineering / Volume 65 / Number 2 / February 1978 / Pages 414-415

Technical Note / dx.doi.org/10.13182/NSE78-A27168

Restrained Acceleration in Iteration

D. R. Vondy, T. B. Fowler

Nuclear Science and Engineering / Volume 65 / Number 2 / February 1978 / Pages 415-416

Technical Note / dx.doi.org/10.13182/NSE78-A27169

Some Observations on Transverse Leakage Approximations in Multidimensional Transport Theory

M. M. R. Williams, J. M. Kallfelz

Nuclear Science and Engineering / Volume 65 / Number 2 / February 1978 / Pages 416-419

Technical Note / dx.doi.org/10.13182/NSE78-A27170

The Effect of Non-1/v Absorbers on Thermal-Neutron Transport in Finite Size Assemblies of Water and Heavy Water

R. M. Bansal, S. P. Tewari

Nuclear Science and Engineering / Volume 65 / Number 2 / February 1978 / Pages 419-422

Technical Note / dx.doi.org/10.13182/NSE78-A27171

Number 3

Table of Contents
Fundamental Aspects of Nuclear Reactor Fuel Elements(Charles F. Bonilla)
Measurement of Unsteady Fluid Dynamic Phenomena(Joel Weisman)
Comments on “Laser Fusion Hydrodynamics Calculations”(J. Ligou)
Reply to “Comments on ‘Laser Fusion Hydrodynamics Calculations’”(Gregory A. Moses)

Thermal Expansion Worths for a Liquid-Metal Fast Breeder Reactor Inferred from Small-Sample Reactivity Measurements

B. Wei-Teh Lee, R. E. Kaiser, J. T. Hitchcock, C. S. Russell

Nuclear Science and Engineering / Volume 65 / Number 3 / March 1978 / Pages 429-440

Technical Paper / dx.doi.org/10.13182/NSE78-A27174

An Evaluation of ENDF/B-IV and Hansen-Roach Uranium-233 Cross Sections for Use in Criticality Calculations

S. R. McNeany, J. D. Jenkins

Nuclear Science and Engineering / Volume 65 / Number 3 / March 1978 / Pages 441-453

Technical Paper / dx.doi.org/10.13182/NSE78-A27175

Neutron Capture and Fission Cross Sections of Plutonium-241

L. W. Weston, J. H. Todd

Nuclear Science and Engineering / Volume 65 / Number 3 / March 1978 / Pages 454-463

Technical Paper / dx.doi.org/10.13182/NSE78-A27176

Predictions of Fission Cross Sections in the 3- to 5-MeV Neutron Energy Range

J. W. Behrens, R. J. Howerton

Nuclear Science and Engineering / Volume 65 / Number 3 / March 1978 / Pages 464-467

Technical Paper / dx.doi.org/10.13182/NSE65-464

Practical Formalisms for Nuclear Data Representation in Evaluated Nuclear Data Files in the Unresolved Resonance Energy Region

Y. Gur, S. Yiftah

Nuclear Science and Engineering / Volume 65 / Number 3 / March 1978 / Pages 468-476

Technical Paper / dx.doi.org/10.13182/NSE78-A27178

Consistent Utilization of Shielding Benchmark Experiments

A. D'Angelo, A. Oliva, G. Palmiotti, M. Salvatores, S. Zero

Nuclear Science and Engineering / Volume 65 / Number 3 / March 1978 / Pages 477-491

Technical Paper / dx.doi.org/10.13182/NSE78-A27179

Substitution Measurements on 28-Fuel-Rod Critical Clusters in D₂O and Their Analysis by the Second-Order Perturbation Method

Kiminori Shiba

Nuclear Science and Engineering / Volume 65 / Number 3 / March 1978 / Pages 492-507

Technical Paper / dx.doi.org/10.13182/NSE78-A27180

A Linear Stability Analysis of Reactors with a Delayed Temperature Feedback

Trine-Yie Dawn, Chio-Min Yang

Nuclear Science and Engineering / Volume 65 / Number 3 / March 1978 / Pages 508-513

Technical Paper / dx.doi.org/10.13182/NSE78-A27181

The C_N Method of Solving the Transport Equation: Application to Cylindrical Geometry

Alain Kavenoky

Nuclear Science and Engineering / Volume 65 / Number 3 / March 1978 / Pages 514-531

Technical Paper / dx.doi.org/10.13182/NSE78-A27182

Iterative Solution of the Neutron Transport Equation by Means of Diffusion Techniques

M. Michelini

Nuclear Science and Engineering / Volume 65 / Number 3 / March 1978 / Pages 532-539

Technical Paper / dx.doi.org/10.13182/NSE78-A27183

Neutron Heating Sensitivity to Cross-Section Variations in a Controlled Thermonuclear Reactor Blanket

B. Arcipiani, G. Palmiotti, M. Salvatores

Nuclear Science and Engineering / Volume 65 / Number 3 / March 1978 / Pages 540-544

Technical Note / dx.doi.org/10.13182/NSE78-A27184

Production of Uranium-232 in a 1200-MW(e) Liquid-Metal Fast Breeder Reactor

F. M. Mann, R. E. Schenter

Nuclear Science and Engineering / Volume 65 / Number 3 / March 1978 / Pages 544-547

Technical Note / dx.doi.org/10.13182/NSE78-A27185

Measurement of the Uranium-238 Doppler Effect in Gas-Cooled Fast Reactor Critical Assemblies

S. K. Bhattacharyya, R. B. Pond

Nuclear Science and Engineering / Volume 65 / Number 3 / March 1978 / Pages 548-553

Technical Note / dx.doi.org/10.13182/NSE78-A27186

On the Energy Dependence of the Total Cross Section of the Reaction ²H(d, n)³He

M. Drosg

Nuclear Science and Engineering / Volume 65 / Number 3 / March 1978 / Pages 553-554

Technical Note / dx.doi.org/10.13182/NSE78-A27187

A First-Order Approximation to Fast-Neutron Penetration Spectra for Non-Normally Incident Neutrons on Water Slabs

William H. Miller, David Hollabaugh, Walter Meyer

Nuclear Science and Engineering / Volume 65 / Number 3 / March 1978 / Pages 554-557

Technical Note / dx.doi.org/10.13182/NSE78-A27188

Effects of Isotopic Abundance on Kerma in Naturally Occurring Targets: Chlorine

Martin S. Spergel, Otto W. Lazareth

Nuclear Science and Engineering / Volume 65 / Number 3 / March 1978 / Pages 558-560

Technical Note / dx.doi.org/10.13182/NSE78-A27189

Expansion About a Local Maxwellian for Evaluating the Spatially Dependent Neutron Spectrum

V. G. Molinari, R. Simonini

Nuclear Science and Engineering / Volume 65 / Number 3 / March 1978 / Pages 560-565

Technical Note / dx.doi.org/10.13182/NSE78-A27190

Kinetic Parameters of the University of Maryland Reactor by the Interval-Distribution Method

John A. Rawlins, S. Christian Simonson III

Nuclear Science and Engineering / Volume 65 / Number 3 / March 1978 / Pages 565-567

Technical Note / dx.doi.org/10.13182/NSE78-A27191