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Volume 68

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Number 1

Table of Contents
Nuclear Reactor Safety(Saul Levine)

Second-Order Generalized Perturbation Theory for Source-Driven Systems

E. Greenspan, D. Gilai, E. M. Oblow

Nuclear Science and Engineering / Volume 68 / Number 1 / October 1978 / Pages 1-9

Technical Paper / dx.doi.org/10.13182/NSE68-1-1

The Probability Table Method and Correlated Data

S. Pearlstein

Nuclear Science and Engineering / Volume 68 / Number 1 / October 1978 / Pages 10-18

Technical Paper / dx.doi.org/10.13182/NSE78-A27265

Monte Carlo Aspects of Contributons

A. Dubi, S. A. W. Gerstl, Donald J. Dudziak

Nuclear Science and Engineering / Volume 68 / Number 1 / October 1978 / Pages 19-30

Technical Paper / dx.doi.org/10.13182/NSE78-A27266

Some Fundamental Relations Between Classical Problems of Transport Theory

P. Benoist

Nuclear Science and Engineering / Volume 68 / Number 1 / October 1978 / Pages 31-37

Technical Paper / dx.doi.org/10.13182/NSE78-A27267

Differential Elastic and Inelastic Scattering of 7- to 15-MeV Neutrons from Beryllium

H. H. Hogue, P. L. Von Behren, D. H. Epperson, S. G. Glendinning, P. W. Lisowski, C. E. Nelson, H. W. Newson, F. O. Purser, W. Tornow, C. R. Gould, L. W. Seagondollar

Nuclear Science and Engineering / Volume 68 / Number 1 / October 1978 / Pages 38-42

Technical Paper / dx.doi.org/10.13182/NSE78-A27268

Measurement of the Uranium-238 to Uranium-235 Fission Cross-Section Ratio for Neutron Energies Between 0.1 and 25 MeV

F. C. Difilippo, R. B. Perez, G. de Saussure, D. K. Olsen, R. W. Ingle

Nuclear Science and Engineering / Volume 68 / Number 1 / October 1978 / Pages 43-54

Technical Paper / dx.doi.org/10.13182/NSE78-A27269

Analysis of Neutron Emission Spectra from 14-MeV Neutron Reactions

S. Pearlstein

Nuclear Science and Engineering / Volume 68 / Number 1 / October 1978 / Pages 55-60

Technical Paper / dx.doi.org/10.13182/NSE78-A27270

Optimum Burnup Distribution in a Continuously Fueled Reactor

A. L. Wight, P. Girouard

Nuclear Science and Engineering / Volume 68 / Number 1 / October 1978 / Pages 61-72

Technical Paper / dx.doi.org/10.13182/NSE78-A27271

Transient Pressurization and Transport of a Two-Component Gas Within Interconnected Porosity of Solid Mixed-Oxide Fuel

J. R. Hofmann

Nuclear Science and Engineering / Volume 68 / Number 1 / October 1978 / Pages 73-90

Technical Paper / dx.doi.org/10.13182/NSE78-A27272

Wigner-Wilkins Thermalization Revisited

J. Grzesik

Nuclear Science and Engineering / Volume 68 / Number 1 / October 1978 / Pages 91-94

Technical Note / dx.doi.org/10.13182/NSE78-A27273

Sensitivity of Primary Knock-On Atom Spectra and Displacement per Atom Cross Sections to Different Secondary Neutron Energy and Angular Distributions and “In-Group” Weighting Schemes

T. A. Gabriel, B. L. Bishop

Nuclear Science and Engineering / Volume 68 / Number 1 / October 1978 / Pages 94-99

Technical Note / dx.doi.org/10.13182/NSE78-A27274

Two-Media Problems in Two-Group Neutron Transport Theory

Yuji Ishiguro, Roberto D. M. Garcia

Nuclear Science and Engineering / Volume 68 / Number 1 / October 1978 / Pages 99-110

Technical Note / dx.doi.org/10.13182/NSE78-A27275

Dynamic Measurements of a Nuclear Reactor Using Low-Peak-Factor Excitation Signals

J. O. Flower, S. C. Forge, N. G. Radcliffe, C. B. Roust

Nuclear Science and Engineering / Volume 68 / Number 1 / October 1978 / Pages 110-115

Technical Note / dx.doi.org/10.13182/NSE78-A27276

Calculations of UH₃ Critical Masses for Various Uranium Enrichments

Francis H. Lewis, Patrick D. Soran

Nuclear Science and Engineering / Volume 68 / Number 1 / October 1978 / Pages 116-125

Technical Note / dx.doi.org/10.13182/NSE78-A27277

Multilevel Resonance Parameters of Plutonium-241

L. W. Weston, J. H. Todd

Nuclear Science and Engineering / Volume 68 / Number 1 / October 1978 / Pages 125-128

Technical Note / dx.doi.org/10.13182/NSE78-A27278

Measurement of the Fission Cross Section of Plutonium-241 Relative to Uranium-235 for Neutron Energies from 1 keV to 30 MeV

G. W. Carlson, J. W. Behrens

Nuclear Science and Engineering / Volume 68 / Number 1 / October 1978 / Pages 128-132

Technical Note / dx.doi.org/10.13182/NSE78-A27279

Best Values for the Cross Section of the Neutron Standard Reaction ¹⁰B(n,α₁)⁷ Li in the Range from 0.1 to 2.0 MeV

Horst Liskien, Eric Wattecamps

Nuclear Science and Engineering / Volume 68 / Number 1 / October 1978 / Pages 132-137

Technical Note / dx.doi.org/10.13182/NSE78-A27280

Thermal-Neutron Steady-State Spectra in Pure and Poisoned Light Water Assemblies

K. Swaminathan, S. P. Tewari, R. M. Bansal

Nuclear Science and Engineering / Volume 68 / Number 1 / October 1978 / Pages 137-140

Technical Note / dx.doi.org/10.13182/NSE78-A27281

Self-Initialization of the RELAP4 Code Momentum Equation

R. C. Kern, M. T. Hsu

Nuclear Science and Engineering / Volume 68 / Number 1 / October 1978 / Pages 141-143

Technical Note / dx.doi.org/10.13182/NSE78-A27282

Numerical Simulation of Hydrodynamic Impact Loads on Cylinders

B. D. Nichols, C. W. Hirt

Nuclear Science and Engineering / Volume 68 / Number 1 / October 1978 / Pages 143-148

Technical Note / dx.doi.org/10.13182/NSE78-A27283

Number 2

Table of Contents
MACK-IV(M. A. Abdou, Y. Gohar, R. Q. Wright)
Plasma Physics(Albert Simon)
Two-Phase Flow and Heat Transfer(Walter L. Kirchner)
Foundations of Nuclear Engineering(R. K. Osborn)
Computational Methods in Engineering and Science(James J. Duderstadt, William R. Martin)
Fusion-Fission Analogy and Tnτ Criterion for Fusion Plasmas(J. Rand McNally, Jr.)

Two-Phase Flow Patterns with High-Pressure Water in a Heated Four-Rod Bundle

C. L. Williams, A. C. Peterson, Jr.

Nuclear Science and Engineering / Volume 68 / Number 2 / November 1978 / Pages 155-169

Technical Paper / dx.doi.org/10.13182/NSE78-A27286

Neutron Flux Monitoring and Data Analysis for Neutron Standard Reaction Cross Sections

O. A. Wasson, R. A. Schrack, G. P. Lamaze

Nuclear Science and Engineering / Volume 68 / Number 2 / November 1978 / Pages 170-182

Technical Paper / dx.doi.org/10.13182/NSE78-A27287

A New Measurement of the ⁶Li(n,α)T Cross Section

G. P. Lamaze, R. A. Schrack, O. A. Wasson

Nuclear Science and Engineering / Volume 68 / Number 2 / November 1978 / Pages 183-188

Technical Paper / dx.doi.org/10.13182/NSE78-A27288

A Measurement of the ¹⁰B(n,αγ)⁷Li Cross Section in the keV Energy Region

R. A. Schrack, G. P. Lamaze, O. A. Wasson

Nuclear Science and Engineering / Volume 68 / Number 2 / November 1978 / Pages 189-196

Technical Paper / dx.doi.org/10.13182/NSE78-A27289

Absolute Neutron Fission Cross Sections of ²³⁵U, ²³⁸U, and ²³⁹Pu at 13.9 and 14.6 MeV

M. Cancé, G. Grenier

Nuclear Science and Engineering / Volume 68 / Number 2 / November 1978 / Pages 197-203

Technical Paper / dx.doi.org/10.13182/NSE78-A27290

Sputtering Calculations with the Discrete-Ordinates Method

T. J. Hoffman, H. L. Dodds, Jr., M. T. Robinson, D. K. Holmes

Nuclear Science and Engineering / Volume 68 / Number 2 / November 1978 / Pages 204-211

Technical Paper / dx.doi.org/10.13182/NSE78-A27291

Cylindrical Source Shielding Equations Utilizing Compact Functions and Including Buildup

J. L. Kamphouse

Nuclear Science and Engineering / Volume 68 / Number 2 / November 1978 / Pages 212-217

Technical Note / dx.doi.org/10.13182/NSE78-A27292

On Several Good Methods for Computing the Distortion Factor Relevant to a Foil Placed in an Exponentially Varying Flux

P. Benoist, V. C. Boffi, P. Grandjean, A. Kavenoky, V. G. Molinari, C. E. Siewert, G. Spiga

Nuclear Science and Engineering / Volume 68 / Number 2 / November 1978 / Pages 217-219

Technical Note / dx.doi.org/10.13182/NSE78-A27293

Reactivity Prediction of Uniform PuO₂-UO₂-Fueled Lattices and Pu(NO₃)₄ Solutions in Light Water

P. Mohanakrishnan, H. C. Huria

Nuclear Science and Engineering / Volume 68 / Number 2 / November 1978 / Pages 220-226

Technical Note / dx.doi.org/10.13182/NSE78-A27294

Neutron Wave Propagation Across an Absorption Discontinuity

Ashok Sadhwani, Ashok Kumar

Nuclear Science and Engineering / Volume 68 / Number 2 / November 1978 / Pages 226-230

Technical Note / dx.doi.org/10.13182/NSE78-A27295

Number 3

Table of Contents
Annual Review of Nuclear Science(W. Bennett Lewis, William R. Conkie, W. McLatchie, B. C. Robertson, John C. Hardy, F. C. Khanna)
Flow Induced Vibration(D. J. Gorman)

The One-Group Neutron Transport Equation and Angular Flux Separability

D. Shalitin, J. J. Wagschal, Y. Yeivin

Nuclear Science and Engineering / Volume 68 / Number 3 / December 1978 / Pages 243-248

Technical Paper / dx.doi.org/10.13182/NSE78-A27303

Analytic Method for the Numerical Solution of the Integral Transport Equation for a Homogeneous Cylinder

Michael S. Milgram

Nuclear Science and Engineering / Volume 68 / Number 3 / December 1978 / Pages 249-269

Technical Paper / dx.doi.org/10.13182/NSE78-A27304

Statistical Model Analysis of Spin Influence on the Deexcitation of Fission Fragments

D. P. Min, M. Martinot

Nuclear Science and Engineering / Volume 68 / Number 3 / December 1978 / Pages 270-280

Technical Paper / dx.doi.org/10.13182/NSE78-A27305

Detailed Calculations in Energy and Space of Effective Neutron Resonance Cross Sections

José M. Aragonés

Nuclear Science and Engineering / Volume 68 / Number 3 / December 1978 / Pages 281-298

Technical Paper / dx.doi.org/10.13182/NSE78-A27306

The Impact of Aging Mechanisms on Reactor Safety System Performance

E. Oelkers, W. W. Weaver

Nuclear Science and Engineering / Volume 68 / Number 3 / December 1978 / Pages 299-307

Technical Paper / dx.doi.org/10.13182/NSE78-A27307

The Role of Rayleigh-Taylor Instabilities in Fuel-Coolant Interactions

Fred Cooper, John Dienes

Nuclear Science and Engineering / Volume 68 / Number 3 / December 1978 / Pages 308-321

Technical Paper / dx.doi.org/10.13182/NSE78-A27308

Sensitivity Theory for Reactor Thermal-Hydraulics Problems

E. M. Oblow

Nuclear Science and Engineering / Volume 68 / Number 3 / December 1978 / Pages 322-337

Technical Paper / dx.doi.org/10.13182/NSE78-A27309

Multidimensional Effects in Critical Two-Phase Flow

J. R. Travis, C. W. Hirt, W. C. Rivard

Nuclear Science and Engineering / Volume 68 / Number 3 / December 1978 / Pages 338-348

Technical Paper / dx.doi.org/10.13182/NSE78-A27310

Possible Criticality of Protactinium-231

George C. Wu, Lawrence Ruby

Nuclear Science and Engineering / Volume 68 / Number 3 / December 1978 / Pages 349-351

Technical Note / dx.doi.org/10.13182/NSE78-A27311

A Direct Technique for Unfolding Neutron Spectra from Activation Data

Hiroshi Sekimoto

Nuclear Science and Engineering / Volume 68 / Number 3 / December 1978 / Pages 351-356

Technical Note / dx.doi.org/10.13182/NSE78-A27312

Effects of Nuclear Deformation on Neutron Total Cross Sections

L. Zuffi

Nuclear Science and Engineering / Volume 68 / Number 3 / December 1978 / Pages 356-357

Technical Note / dx.doi.org/10.13182/NSE78-A27313

Measurements of the Total Neutron Cross Section of Uranium-233 Between 40 keV and 4.5 MeV

W. P. Poenitz, J. F. Whalen, P. Guenther, A. B. Smith

Nuclear Science and Engineering / Volume 68 / Number 3 / December 1978 / Pages 358-359

Technical Note / dx.doi.org/10.13182/NSE78-A27314

The Fission Cross Sections of Plutonium-239 and Plutonium-242 Relative to Uranium-235 from 0.1 to 10 MeV

J. W. Meadows

Nuclear Science and Engineering / Volume 68 / Number 3 / December 1978 / Pages 360-363

Technical Note / dx.doi.org/10.13182/NSE78-A27315

Best-Estimate Fuel Rod Modeling Techniques

D. A. Niebruegge, E. L. Tolman, C. W. Solbrig

Nuclear Science and Engineering / Volume 68 / Number 3 / December 1978 / Pages 363-368

Technical Note / dx.doi.org/10.13182/NSE78-A27316