Volume 78

Number 1 | Number 2 | Number 3 | Number 4

Number 1

Table of Contents
On “Double Criticality”(Václav Bartošek)
Reply to “On ‘Double Criticality’”(Yuji Ishiguro)
Neutron Lifetime, Generation Time, and Reproduction Time(Jeffery D. Lewins)
Response to “Neutron Lifetime, Generation Time, and Reproduction Time”(Charles R. Marotta)
Comments on “Numerical Calculations of the Global and Local Components of the Neutron Noise Field in Boiling Water Reactors”(Om Pal Singh, T. M. John)
Response to the “Comments on ‘Numerical Calculations of the Global and Local Components of the Neutron Noise Field in Boiling Water Reactors’”(F. C. Difilippo, P. J. Otaduy)
Government Intervention in the Canadian Nuclear Industry(Craig Hosmer)
Stable Isotope Capture Cross Sections from the Oak Ridge Electron Linear Accelerator(R. L. Macklin, R. R. Winters)

Application of the Method of Characteristics to Solution of Nuclear Engineering Problems

Joel Weisman, Adrian Tentner

Nuclear Science and Engineering / Volume 78 / Number 1 / May 1981 / Pages 1-29

Critical Review / dx.doi.org/10.13182/NSE81-A19603

Absolute Neutron Spectrum Measurements in a Lithium Fluoride Integral Assembly for Fusion Reactor Data Assessment

L. J. Perkins, N. Evans, Malcolm C. Scott, B. Y. Underwood

Nuclear Science and Engineering / Volume 78 / Number 1 / May 1981 / Pages 30-43

Technical Paper / dx.doi.org/10.13182/NSE81-A19604

Absolute Measurement of the ⁶Li(n, α)³H Cross Section at 23 keV

J. C. Engdahl, G. F. Knoll, J. C. Robertson

Nuclear Science and Engineering / Volume 78 / Number 1 / May 1981 / Pages 44-52

Technical Paper / dx.doi.org/10.13182/NSE81-A19605

The DP_N Surface Flux Integral Neutron Transport Method for Slab Geometry

Jiri Stepanek

Nuclear Science and Engineering / Volume 78 / Number 1 / May 1981 / Pages 53-65

Technical Paper / dx.doi.org/10.13182/NSE81-A19606

Asymptotically Stable Solutions of Nonlinear Space-Dependent Neutron Kinetics Equations

R. Srivenkatesan, M. S. Trasi

Nuclear Science and Engineering / Volume 78 / Number 1 / May 1981 / Pages 66-73

Technical Paper / dx.doi.org/10.13182/NSE81-A19607

Application of Three-Exponential Representation of Photon Buildup Factors to Water

A. Foderaro, R. J. Hall

Nuclear Science and Engineering / Volume 78 / Number 1 / May 1981 / Pages 74-78

Technical Note / dx.doi.org/10.13182/NSE81-A19608

The Quadrature of the Point Kernel in Shielding Calculations

O. J. Wallace

Nuclear Science and Engineering / Volume 78 / Number 1 / May 1981 / Pages 78-85

Technical Note / dx.doi.org/10.13182/NSE81-A19609

A Nonsingular Point Kernel Integrand

O. J. Wallace

Nuclear Science and Engineering / Volume 78 / Number 1 / May 1981 / Pages 85-88

Technical Note / dx.doi.org/10.13182/NSE81-A19610

Approximations to Neutron Escape Probability and Dancoff Correction

Y. A. Chao, M. B. Yarbrough, A. S. Martinez

Nuclear Science and Engineering / Volume 78 / Number 1 / May 1981 / Pages 89-91

Technical Note / dx.doi.org/10.13182/NSE78-89

Polynomial Expressions for the Neutron Escape Probability

Hem Prabha Raghav

Nuclear Science and Engineering / Volume 78 / Number 1 / May 1981 / Pages 91-96

Technical Note / dx.doi.org/10.13182/NSE78-91

Solution of the Reactor Probability Equation in the Detector Weak-Coupling Limit

Lawrence Ruby

Nuclear Science and Engineering / Volume 78 / Number 1 / May 1981 / Pages 96-97

Technical Note / dx.doi.org/10.13182/NSE81-A19613

A Method for Solving Integral Transport Equation for Pressurized Heavy Water Reactor Cluster Geometry

P. D. Krishnani, K. R. Srinivasan

Nuclear Science and Engineering / Volume 78 / Number 1 / May 1981 / Pages 97-103

Technical Note / dx.doi.org/10.13182/NSE81-A19614

Number 2

Table of Contents
Comment on Approximate Escape Probability Calculations(Iván Lux)
Responses to “Comment on Approximate Escape Probability Calculations”(Yung-An Chao)
Comments on the Tritium Solubility in Lithium Oxide as a Solid Tritium Breeding Material(Shoichi Nasu, Takaaki Tanifuji, Hidefumi Takeshita)
Response to “Comments on the Tritium Solubility in Lithium Oxide as a Solid Tritium Breeding Material”(Robert C. Clemmer)
The Detection of Fissionable Materials by Nondestructive Means(Edward D. Blakeman)
Numerical Heat Transfer and Fluid Flow(Chia-Jung Hsu)
Integral Transport Theory Formalism for Diffusion Coefficient Calculations in Wigner-Seitz Cells(P. Benoist)

Calculation of the Radial and Axial Diffusion Coefficient for a Hexagonal Lattice of a High-Temperature Reactor with Block Elements

P. Köhler

Nuclear Science and Engineering / Volume 78 / Number 2 / June 1981 / Pages 113-120

Technical Paper / dx.doi.org/10.13182/NSE81-A20097

Criticality of 4.3 wt% Uranium-235 Enriched UO₂ Rods in Uranyl Nitrate Solution Containing Gadolinium

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

Nuclear Science and Engineering / Volume 78 / Number 2 / June 1981 / Pages 121-125

Technical Paper / dx.doi.org/10.13182/NSE81-A20098

Fission-Product Energy Release for Times Following Thermal-Neutron Fission of Plutonium-239 and Plutonium-241 Between 2 and 14 000 s

J. K. Dickens, T. A. Love, J. W. McConnell, R. W. Peelle

Nuclear Science and Engineering / Volume 78 / Number 2 / June 1981 / Pages 126-146

Technical Paper / dx.doi.org/10.13182/NSE81-A20099

Uranium-238 Inelastic Neutron Scattering at 82 keV

R. R. Winters, N. W. Hill, R. L. Macklin, J. A. Harvey, D. K. Olsen, G. L. Morgan

Nuclear Science and Engineering / Volume 78 / Number 2 / June 1981 / Pages 147-153

Technical Paper / dx.doi.org/10.13182/NSE81-A20100

Phenomenological Modeling of the Triggering Phase of Small-Scale Steam Explosion Experiments

M. L. Corradini

Nuclear Science and Engineering / Volume 78 / Number 2 / June 1981 / Pages 154-170

Technical Paper / dx.doi.org/10.13182/NSE81-A20101

Exact Solution for Suboptimal Control of Nuclear Reactors with Distributed Parameters

S. H. Kim, Jonghwa Chang

Nuclear Science and Engineering / Volume 78 / Number 2 / June 1981 / Pages 171-175

Technical Note / dx.doi.org/10.13182/NSE81-A20102

Monte Carlo Self-Shielding Corrections for Use with Neutron Spectrum Unfolding Codes

D. J. Brenner

Nuclear Science and Engineering / Volume 78 / Number 2 / June 1981 / Pages 175-177

Technical Note / dx.doi.org/10.13182/NSE81-A20103

Fast Neutron Spectrum in Lithium with a 14-MeV Neutron Source

A. E. Profio, Gad Shani, G. A. Dissanaike

Nuclear Science and Engineering / Volume 78 / Number 2 / June 1981 / Pages 178-182

Technical Note / dx.doi.org/10.13182/NSE81-A20104

A Determination of the Carbon Thermal Neutron Capture Cross Section

W. V. Prestwich, M. A. Islam, T. J. Kennett

Nuclear Science and Engineering / Volume 78 / Number 2 / June 1981 / Pages 182-185

Technical Note / dx.doi.org/10.13182/NSE81-A20105

Decay Rate and Decay Heat Data from Fission Products

K. Shure

Nuclear Science and Engineering / Volume 78 / Number 2 / June 1981 / Pages 185-190

Technical Note / dx.doi.org/10.13182/NSE81-A20106

Number 3

Table of Contents
Comment on the Nonhyperbolicity of Two-Phase Flow Equations(W. S. Liu)
Reply to “Comment on the Nonhyperbolicity of Two-Phase Flow Equations”(Robert W. Lyczkowski)
Nuclear Power and Its Environmental Effects(Emil T. Chanlett)

Transmission of a Gaseous Radioactive Isotope Through an Adsorber Bed

Richard Madey, Jan-Chan Huang, Eugene Pflumm

Nuclear Science and Engineering / Volume 78 / Number 3 / July 1981 / Pages 205-210

Technical Paper / dx.doi.org/10.13182/NSE81-A20298

The Application of Generalized Perturbation Theory and Mathematical Programming to Equilibrium Refueling Studies of a CANDU Reactor

D. Rozon, A. Hébert, D. McNabb

Nuclear Science and Engineering / Volume 78 / Number 3 / July 1981 / Pages 211-226

Technical Paper / dx.doi.org/10.13182/NSE81-A20299

Neutron Streaming in Fast Reactor Slab Lattices and in Cylindrical Channels

E. A. Fischer

Nuclear Science and Engineering / Volume 78 / Number 3 / July 1981 / Pages 227-238

Technical Paper / dx.doi.org/10.13182/NSE81-A20300

Measurements of the ²³⁸U(n, γ) Cross Section at Thermal and Fast Neutron Energies

W. P. Poenitz, L. R. Fawcett, Jr., D. L. Smith

Nuclear Science and Engineering / Volume 78 / Number 3 / July 1981 / Pages 239-247

Technical Paper / dx.doi.org/10.13182/NSE81-1

Neutron Fission Cross-Section Measurement of Americium-241 in the Energy Range from 10 to 1030 keV

W. Hage, K. Wisshak, F. Käppeler

Nuclear Science and Engineering / Volume 78 / Number 3 / July 1981 / Pages 248-258

Technical Paper / dx.doi.org/10.13182/NSE81-A20302

Calculation of Neutron and Gamma-Ray Energy Spectra for Fusion Reactor Shield Design: Comparison with Experiment

R. T. Santoro, R. G. Alsmiller, Jr., J. M. Barnes, G. T. Chapman

Nuclear Science and Engineering / Volume 78 / Number 3 / July 1981 / Pages 259-272

Technical Paper / dx.doi.org/10.13182/NSE81-A20303

Transport Calculation of Gamma Rays Including Bremsstrahlung by the Discrete Ordinates Code PALLAS

K. Takeuchi, S. Tanaka, M. Kinno

Nuclear Science and Engineering / Volume 78 / Number 3 / July 1981 / Pages 273-283

Technical Paper / dx.doi.org/10.13182/NSE81-A20304

One-Dimensional Discrete Ordinates Adjoint Calculations of Cylindrical Target Responses to Plane-Incident Sources

S. A. Dupree, J. E. Morel

Nuclear Science and Engineering / Volume 78 / Number 3 / July 1981 / Pages 284-293

Technical Paper / dx.doi.org/10.13182/NSE81-A20305

Downward Penetration of a Hot Liquid Pool into a Gas-Releasing Miscible Solid Surface

Rouyentan Farhadieh

Nuclear Science and Engineering / Volume 78 / Number 3 / July 1981 / Pages 294-296

Technical Note / dx.doi.org/10.13182/NSE81-A20306

An Equivalence Relation for Annular Absorbers

John F. Carew

Nuclear Science and Engineering / Volume 78 / Number 3 / July 1981 / Pages 296-297

Technical Note / dx.doi.org/10.13182/NSE81-A20307

A Study of Neutron Flux and Source Approximations in Slab Geometry

Frej Wasastjerna

Nuclear Science and Engineering / Volume 78 / Number 3 / July 1981 / Pages 297-304

Technical Note / dx.doi.org/10.13182/NSE81-A20308

Number 4

Table of Contents
Generalized Perturbation Theory for Nonlinear Systems from the Importance Conservation Principle(A. Gandini)
Response to ‘Neutron Lifetime, Generation Time, and Reproduction Time’(C. R. Marot)
Pressure Component Construction … Design and Materials Application(C. E. Knight)

Multigroup Transport Theory. I. Basic Analysis

C. E. Siewert, P. Benoist

Nuclear Science and Engineering / Volume 78 / Number 4 / August 1981 / Pages 311-314

Technical Paper / dx.doi.org/10.13182/NSE81-A21364

Multigroup Transport Theory. II. Numerical Results

R. D. M. Garcia, C. E. Siewert

Nuclear Science and Engineering / Volume 78 / Number 4 / August 1981 / Pages 315-323

Technical Paper / dx.doi.org/10.13182/NSE81-A21365

Evaluation of the ²³Na(n,2n) ²²Na Reaction for ENDF/B-V

D. C. Larson

Nuclear Science and Engineering / Volume 78 / Number 4 / August 1981 / Pages 324-332

Technical Paper / dx.doi.org/10.13182/NSE81-A21366

Total Neutron Cross Sections of Heavy Nuclei

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

Nuclear Science and Engineering / Volume 78 / Number 4 / August 1981 / Pages 333-341

Technical Paper / dx.doi.org/10.13182/NSE81-A21367

Space-Energy Few-Group Neutron Cross Sections for Large, Complex Core Calculations

L. B. Freeman

Nuclear Science and Engineering / Volume 78 / Number 4 / August 1981 / Pages 342-358

Technical Paper / dx.doi.org/10.13182/NSE81-A21368

Measurement of the Cross Section for the ⁷Li(n,n't)⁴He Reaction in the 7- to 9-MeV Energy Range

Donald L. Smith, Manuel M. Bretscher, J. W. Meadows

Nuclear Science and Engineering / Volume 78 / Number 4 / August 1981 / Pages 359-369

Technical Paper / dx.doi.org/10.13182/NSE81-A21369

Neutron Total Cross Section and Resonance Parameters of ²³¹Pa

Abdel-Razik Z. Hussein, J. A. Harvey, N. W. Hill, J. R. Patterson

Nuclear Science and Engineering / Volume 78 / Number 4 / August 1981 / Pages 370-376

Technical Paper / dx.doi.org/10.13182/NSE81-A21370

Measurement of (n, α) Cross Sections of Chromium, Iron, and Nickel in the 5- to 10-MeV Neutron Energy Range

A. Paulsen, H. Liskien, F. Arnotte, R. Widera

Nuclear Science and Engineering / Volume 78 / Number 4 / August 1981 / Pages 377-385

Technical Paper / dx.doi.org/10.13182/NSE81-A21371

Kinetic Studies of the Reaction of Plutonium Hydride with Oxygen

Jerry L. Stakebake

Nuclear Science and Engineering / Volume 78 / Number 4 / August 1981 / Pages 386-392

Technical Paper / dx.doi.org/10.13182/NSE81-A21372

An Anomaly in the Use of Perturbation Theory

F. Rahnema, G. C. Pomraning

Nuclear Science and Engineering / Volume 78 / Number 4 / August 1981 / Pages 393-395

Technical Note / dx.doi.org/10.13182/NSE81-A21373

HYPERFUSE: A Hypervelocity Inertial Confinement System for Fusion Energy Production and Fission Waste Transmutation

Henry Makowitz, James R. Powell, Richard Wiswall

Nuclear Science and Engineering / Volume 78 / Number 4 / August 1981 / Pages 395-404

Technical Note / dx.doi.org/10.13182/NSE81-A21374

Low-Energy Nuclear Fusion Data and Their Relation to Magnetic and Laser Fusion

Nelson Jarmie

Nuclear Science and Engineering / Volume 78 / Number 4 / August 1981 / Pages 404-412

Technical Note / dx.doi.org/10.13182/NSE81-A21375

Neutrons from ¹¹B + ¹¹B Compared with Other Sources of Neutrons from ¹¹B + p Burn

Edwin Norbeck

Nuclear Science and Engineering / Volume 78 / Number 4 / August 1981 / Pages 412-414

Technical Note / dx.doi.org/10.13182/NSE81-A21376

Measurement of the Average Activation Cross Section for the Reaction ⁶³Cu(n, α)⁶⁰Co in the Spontaneous Fission Neutron Field of Californium-252

G. Winkler, V. Spiegel, C. M. Eisenhauer, D. L. Smith

Nuclear Science and Engineering / Volume 78 / Number 4 / August 1981 / Pages 415-419

Technical Note / dx.doi.org/10.13182/NSE81-A21377

Measurement of the ⁵³Cr(n, p)⁵³V Cross Section Below 9.4 MeV Using a Sample Transport Facility

Donald L. Smith, J. W. Meadows, Frank F. Porta

Nuclear Science and Engineering / Volume 78 / Number 4 / August 1981 / Pages 420-424

Technical Note / dx.doi.org/10.13182/NSE81-A21378

KINGLET Critical Assembly: An Experiment with Flowing Fissile Solution

T. F. Wimett, H. C. Paxton

Nuclear Science and Engineering / Volume 78 / Number 4 / August 1981 / Pages 425-431

Technical Note / dx.doi.org/10.13182/NSE81-A21379

Steam Generator Flow Instability Modeling During the Reflood Stage of a Loss-of-Coolant Accident

D. Y. Hsia, P. Griffith

Nuclear Science and Engineering / Volume 78 / Number 4 / August 1981 / Pages 431-437

Technical Note / dx.doi.org/10.13182/NSE81-A21380