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Volume 69

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Number 1

Table of Contents
Annual Review of Energy: Volume 2(William G. Pollard)
Isotope Separation(Abraham S. Berman)
Modern Formulas for Statics and Dynamics: A Stress and Strain Approach(Robert P. Zerwekh)
Basic Nuclear Engineering(Andrew Robeson)
Transport Equations for Contribuions(S. A. W. Gerstl, J. W. Painter)

A Possible Estimation of In-Process Inventory in Enrichment Cascades

I. Kiss, Sz. Vass

Nuclear Science and Engineering / Volume 69 / Number 1 / January 1979 / Pages 1-5

Technical Paper / dx.doi.org/10.13182/NSE79-A21278

Angular Effects in Toroidal Diffusion

G. C. Pomraning

Nuclear Science and Engineering / Volume 69 / Number 1 / January 1979 / Pages 6-13

Technical Paper / dx.doi.org/10.13182/NSE79-A21279

Theoretical Variations in the Concentration of Tritium in the Heavy Water in CANDU Reactors Caused by the ³He(n,p)³H Reaction

R. M. Holford, R. V. Osborne

Nuclear Science and Engineering / Volume 69 / Number 1 / January 1979 / Pages 14-21

Technical Paper / dx.doi.org/10.13182/NSE79-A21280

Elastic and Inelastic Scattering of 7- to 14-MeV Neutrons from Lithium-6 and Lithium-7

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

Nuclear Science and Engineering / Volume 69 / Number 1 / January 1979 / Pages 22-29

Technical Paper / dx.doi.org/10.13182/NSE79-A21281

Neutron Total Cross-Section Measurements of ⁹Be, ^10,11B, and ^12,13C from 1.0 to 14 MeV Using the ⁹Be(d,n)¹⁰B Reaction as a “White” Neutron Source

G. F. Auchampaugh, S. Plattard, N. W. Hill

Nuclear Science and Engineering / Volume 69 / Number 1 / January 1979 / Pages 30-38

Technical Paper / dx.doi.org/10.13182/NSE79-A21282

Neutron Capture Cross-Section Ratios of Plutonium-240 and Plutonium-242 Versus Gold-197 in the Energy Range from 50 to 250 keV

K. Wisshak, F. Käppeler

Nuclear Science and Engineering / Volume 69 / Number 1 / January 1979 / Pages 39-46

Technical Paper / dx.doi.org/10.13182/NSE79-A21283

A Measurement of the Subthreshold Neutron Fission Cross Section of Plutonium-240 in the Energy Range from 10 to 250 keV

K. Wisshak, F. Käppeler

Nuclear Science and Engineering / Volume 69 / Number 1 / January 1979 / Pages 47-54

Technical Paper / dx.doi.org/10.13182/NSE79-A21284

Fick's Law and the Neutron Slowing Down Length in Hydrogenous Moderators

Carlos Gago B.

Nuclear Science and Engineering / Volume 69 / Number 1 / January 1979 / Pages 55-64

Technical Paper / dx.doi.org/10.13182/NSE79-A21285

Determination of Power Reactor Resonance by the Rod-Drop Method

Edward L. H. Tang

Nuclear Science and Engineering / Volume 69 / Number 1 / January 1979 / Pages 65-75

Technical Paper / dx.doi.org/10.13182/NSE79-A21286

Monte Carlo Source Biasing Optimization

T. J. Hoffman

Nuclear Science and Engineering / Volume 69 / Number 1 / January 1979 / Pages 76-77

Technical Paper / dx.doi.org/10.13182/NSE79-A21287

An Empirical Formula Predicting Shutdown Dose Rate of the Recirculation Pipes in Boiling Water Reactors

Shunsuke Uchida, Masao Kitamura, Makoto Kukuchi, Hideo Yusa, Katsumi Ohsumi, Yasunori Matsushima

Nuclear Science and Engineering / Volume 69 / Number 1 / January 1979 / Pages 78-85

Technical Note / dx.doi.org/10.13182/NSE79-A21288

Effects of Energy Losses of Arbitrary Magnitude on Fuel Quality, Vapor Density, and Bubble Diameter in an Idealized Expansion of Mixtures of UO₂ and Sodium

Hugo W. Bertini, Janice S. White

Nuclear Science and Engineering / Volume 69 / Number 1 / January 1979 / Pages 85-94

Technical Note / dx.doi.org/10.13182/NSE79-A21289

On the Stability of the Flow of Thin Liquid-Lithium Films

James E. Howard

Nuclear Science and Engineering / Volume 69 / Number 1 / January 1979 / Pages 94-99

Technical Note / dx.doi.org/10.13182/NSE79-A21290

Helium Production in Stainless Steel

B. Goel

Nuclear Science and Engineering / Volume 69 / Number 1 / January 1979 / Pages 99-104

Technical Note / dx.doi.org/10.13182/NSE79-A21291

The Importance of Subthreshold Fission Phenomena in Certain Applications of Fission Threshold Detectors: An Example of Neptunium-237 for Nondestructive Assay

F. C. Difllippo, G. L. Ragan

Nuclear Science and Engineering / Volume 69 / Number 1 / January 1979 / Pages 104-107

Technical Note / dx.doi.org/10.13182/NSE79-A21292

Effect of ⁶Li + ⁶Li Reactions in a Fusion Reactor Operating on ⁶Li(p, α)³He

Lawrence Ruby, Tai-Ping Lung

Nuclear Science and Engineering / Volume 69 / Number 1 / January 1979 / Pages 107-109

Technical Note / dx.doi.org/10.13182/NSE79-A21293

Measurement of Cross Sections for the ²⁷Al(n, n′γ)²⁷Al Reaction Near Threshold

Donald L. Smith

Nuclear Science and Engineering / Volume 69 / Number 1 / January 1979 / Pages 109-114

Technical Note / dx.doi.org/10.13182/NSE79-A21294

Eigenvalue Spectrum of Multiplying Slabs and Spheres for Monoenergetic Neutrons with Anisotropic Scattering

E. B. Dahl, N. G. Sjöstrand

Nuclear Science and Engineering / Volume 69 / Number 1 / January 1979 / Pages 114-125

Technical Note / dx.doi.org/10.13182/NSE69-114

Number 2

Table of Contents
Data Analysis in Time-of-Flight Measurements of Spontaneous Fission Spectra(A. Chalupka)
Power Generation(Dick Duffey)

Neutron-Induced Fission in a DT-Plutonium Plasma. Part I: Fission Fragment Slowing Down

S. T. Perkins

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 137-146

Technical Paper / dx.doi.org/10.13182/NSE79-A20605

Neutron-Induced Fission in a DT-Plutonium Plasma. Part II: Enhancement of Neutron Production and Fusion Rate

S. T. Perkins

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 147-155

Technical Paper / dx.doi.org/10.13182/NSE79-A20606

The F_N Method in Neutron-Transport Theory. Part I: Theory and Applications

C. E. Siewert, P. Benoist

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 156-160

Technical Paper / dx.doi.org/10.13182/NSE79-1

The F_N Method in Neutron-Transport Theory. Part II: Applications and Numerical Results

P. Grandjean, C. E. Siewert

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 161-168

Technical Paper / dx.doi.org/10.13182/NSE79-A20608

Spectral Fine-Structure Effects on Material and Doppler Reactivity Worths

E. Greenspan, Y. Karni

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 169-190

Technical Paper / dx.doi.org/10.13182/NSE79-A20609

Neutron Scattering Cross Sections of Uranium-238

L. E. Beghian, G. H. R. Kegel, T. V. Marcella, B. K. Barnes, G. P. Couchell, J. J. Egan, A. Mittler, D. J. Pullen, W. A. Schier

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 191-201

Technical Paper / dx.doi.org/10.13182/NSE79-A20610

Measurement and Resonance Analysis of Neutron Transmission Through Uranium-238

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

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 202-222

Technical Paper / dx.doi.org/10.13182/NSE79-A20611

Differential Neutron Scattering Cross Sections of Lithium-6 and Lithium-7 for Neutrons of 4 to 7.5 MeV Energy

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

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 223-230

Technical Paper / dx.doi.org/10.13182/NSE79-A20612

Critical Experiments on Light Water Lattices of UO₂ and Gd₂O₃ Rods

Tohru Haga, Sadao Hanazawa, Toshio Kimura

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 231-244

Technical Paper / dx.doi.org/10.13182/NSE79-A20613

Criticality of a Slab Reactor with Finite Reflectors

Trine-Yie Dawn

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 245-250

Technical Paper / dx.doi.org/10.13182/NSE79-A20614

A Model for the Prediction of Shutdown Margin for Boiling Water Reactors

Warren F. Witzig, Ross T. Thomas

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 251-263

Technical Paper / dx.doi.org/10.13182/NSE79-A20615

Fast Integral Modeling of Hypothetical Core Disruptive Accidents in Liquid-Metal Fast Breeder Reactors

C. J. Mueller, J. K. Vaurio

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 264-278

Technical Paper / dx.doi.org/10.13182/NSE79-A20616

Network Computations Using a Transient Two-Phase Velocity Difference Model

Robert W. Lyczkowski, Delwin C. Mecham, Charles W. Solbrig

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 279-289

Technical Paper / dx.doi.org/10.13182/NSE79-A20617

Laminar, Transition, and Turbulent Parallel Flow Pressure Drop Across Wire-Wrap-Spaced Rod Bundles

F. C. Engel, R. A. Markley, A. A. Bishop

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 290-296

Technical Paper / dx.doi.org/10.13182/NSE79-A20618

Multichannel Model for Relocation of Molten Fuel Cladding in Unprotected Loss-of-Flow Accidents in Liquid-Metal Fast Breeder Reactors

M. Ishii, W. L. Chen, M. A. Grolmes

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 297-318

Technical Paper / dx.doi.org/10.13182/NSE79-2

Pressure Pulses Generated by Gas Released from a Breached Fuel Element

Ting-Shu Wu

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 319-325

Technical Paper / dx.doi.org/10.13182/NSE79-A20620

Introduction of the Quasi-Static Synthesis Method for Solution of Space-Time Reactor Kinetics Problems

Bruce I. Hauss, William E. Kastenberg

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 326-333

Technical Note / dx.doi.org/10.13182/NSE79-A20621

Measurement and Calculation of Average Activation Cross Sections in the Spontaneous Fission Neutron Field of ²⁵²Cf

W. Mannhart, W. G. Alberts

Nuclear Science and Engineering / Volume 69 / Number 2 / February 1979 / Pages 333-338

Technical Note / dx.doi.org/10.13182/NSE79-A20622

Number 3

Table of Contents
Approximation to Neutron Escape Probability for Slab and Cylinder(Iván Lux, István Vidovszky)
Reply to the Comments by Lux and Vidovszky on an Approximation to Neutron Escape Probability(Yung-An Chao)
The Concept of Energy(John P. Howe)
A Computational Study of the Density and Temperature Distribution in a Freely Expanding Uranium Hexafluoride Gas(H. Mikami)

Exact Statistical Analysis of Nonlinear Dynamic Power Reactor Models by the Fokker-Planck Method. Part II: Reactor with On-Off Control

A. F. Debosscher, W. L. Dutre

Nuclear Science and Engineering / Volume 69 / Number 3 / March 1979 / Pages 347-353

Technical Paper / dx.doi.org/10.13182/NSE79-A19951

Exact Statistical Analysis of Nonlinear Dynamic Power Reactor Models by the Fokker-Planck Method. Part III: Reactor with Temperature Feedback

A. F. Debosscher

Nuclear Science and Engineering / Volume 69 / Number 3 / March 1979 / Pages 354-362

Technical Paper / dx.doi.org/10.13182/NSE79-A19952

A Random Geometry Model in Criticality Calculations of Solutions Containing Raschig Rings

Shi-Ping Teng, Duaine G. Lindstrom

Nuclear Science and Engineering / Volume 69 / Number 3 / March 1979 / Pages 363-366

Technical Paper / dx.doi.org/10.13182/NSE79-A19953

Neutron Diffusion in Water Containing 1/v and Non-1/v Absorbers

R. M. Bansal, S. P. Tewari, L. S. Kothari

Nuclear Science and Engineering / Volume 69 / Number 3 / March 1979 / Pages 367-374

Technical Paper / dx.doi.org/10.13182/NSE79-A19954

Total Neutron Cross Section for Americium-241

Thomas W. Phillips, Robert E. Howe

Nuclear Science and Engineering / Volume 69 / Number 3 / March 1979 / Pages 375-377

Technical Paper / dx.doi.org/10.13182/NSE79-A19955

Neutron-Photon Multigroup Cross Sections for Neutron Energies 60 MeV

R. G. Alsmiller, Jr., J. Barish

Nuclear Science and Engineering / Volume 69 / Number 3 / March 1979 / Pages 378-388

Technical Paper / dx.doi.org/10.13182/NSE79-A19956

Application of Least-Squares Method to Decay Heat Evaluation

F. Schmittroth, R. E. Schenter

Nuclear Science and Engineering / Volume 69 / Number 3 / March 1979 / Pages 389-397

Technical Paper / dx.doi.org/10.13182/NSE79-A19957

The Development of Maneuvering Strategies Using Optimal Control Theory

D. D. Ebert, W. B. Terney, E. A. Williamson, Jr., N. R. Gomm

Nuclear Science and Engineering / Volume 69 / Number 3 / March 1979 / Pages 398-410

Technical Paper / dx.doi.org/10.13182/NSE79-A19958

Experiments and Nonequilibrium Analysis of Pipe Blowdown

W. S. Winters, Jr., H. Merte, Jr.

Nuclear Science and Engineering / Volume 69 / Number 3 / March 1979 / Pages 411-429

Technical Paper / dx.doi.org/10.13182/NSE79-A19959

Complex Buckling Modes in Asymmetric Cell lattices

R. P. Hughes

Nuclear Science and Engineering / Volume 69 / Number 3 / March 1979 / Pages 430-432

Technical Note / dx.doi.org/10.13182/NSE79-A19960

Gamma-Ray Dose Rate Conversion and Buildup Factors

K. Shure

Nuclear Science and Engineering / Volume 69 / Number 3 / March 1979 / Pages 432-436

Technical Note / dx.doi.org/10.13182/NSE79-A19961

Tchebycheff-Fitted Berger Coefficients for Eisenhauer-Simmons Gamma-Ray Buildup Factors in Ordinary Concrete

A. B. Chilton

Nuclear Science and Engineering / Volume 69 / Number 3 / March 1979 / Pages 436-438

Technical Note / dx.doi.org/10.13182/NSE79-A19962

Inertial Confinement Fusion and Long-Term Nuclear Waste Management

Heiner Meldner

Nuclear Science and Engineering / Volume 69 / Number 3 / March 1979 / Pages 438-441

Technical Note / dx.doi.org/10.13182/NSE79-A19963