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Volume 67

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Number 1

Table of Contents
The Thermal-Hydraulics of a Boiling Water Nuclear Reactor(P. A. Lottes)
Note on Prediction of Monte Carlo Errors(Iván Lux)
Production of Uranium-232 in a 1200-MW(e) Liquid-Metal Fast Breeder Reactor(F. M. Mann, R. E. Schenter)

Deposition of Iron Oxide on Heated Surfaces in Boiling Water

Yamato Asakura, Makoto Kikuchi, Shunsuke Uchida, Hideo Yusa

Nuclear Science and Engineering / Volume 67 / Number 1 / July 1978 / Pages 1-7

Technical Paper / dx.doi.org/10.13182/NSE78-6

A Method for Rapid Detection of Unexpected Reactivity Insertion into a Nuclear Reactor

Hideki Kokame, Yoshikazu Nishikawa

Nuclear Science and Engineering / Volume 67 / Number 1 / July 1978 / Pages 8-18

Technical Paper / dx.doi.org/10.13182/NSE78-A27233

Theoretical Analysis of Coupled-Core Reactors with the Method of the Moderator Region Response Function

Minoru Shinkawa, Yoshihiro Yamane, Kojiro Nishina, Hajime Tamagawa

Nuclear Science and Engineering / Volume 67 / Number 1 / July 1978 / Pages 19-33

Technical Paper / dx.doi.org/10.13182/NSE78-A27234

Neutron Inelastic Scattering Cross Sections for Natural Chromium Determined from the (n,n′γ) Reaction

P. T. Karatzas, G. P. Couchell, B. K. Barnes, L. E. Beghian, P. Harihar, A. Mittler, D. J. Pullen, E. Sheldon, N. B. Sullivan

Nuclear Science and Engineering / Volume 67 / Number 1 / July 1978 / Pages 34-53

Technical Paper / dx.doi.org/10.13182/NSE78-A27235

Neutron Capture and Transmission Measurements on Fission Product Palladium-107

U. N. Singh, R. C. Block, Y. Nakagome

Nuclear Science and Engineering / Volume 67 / Number 1 / July 1978 / Pages 54-60

Technical Paper / dx.doi.org/10.13182/NSE78-A27236

Use of Variational Techniques for the Estimation of Neutron Detection Efficiency

Sheng-Chi Lin, J. C. Robinson, D. L. Selby

Nuclear Science and Engineering / Volume 67 / Number 1 / July 1978 / Pages 61-73

Technical Paper / dx.doi.org/10.13182/NSE78-A27237

Neutron Spectra and Tritium Production Measurements in a Lithium Sphere to Check Fusion Reactor Blanket Calculations

Herbert Bachmann, Ulrike Fritscher, Friedbert W. Kappler, Detlef Rusch, Heinrich Werle, Hans W. Wiese

Nuclear Science and Engineering / Volume 67 / Number 1 / July 1978 / Pages 74-84

Technical Paper / dx.doi.org/10.13182/NSE78-A27238

A Unified Derivation of the Various Definitions of Lattice Cell Diffusion Coefficients

R. P. Hughes

Nuclear Science and Engineering / Volume 67 / Number 1 / July 1978 / Pages 85-90

Technical Paper / dx.doi.org/10.13182/NSE78-A27239

Higher Order Time-Dependent Generalized Perturbation Theory

Augusto Gandini

Nuclear Science and Engineering / Volume 67 / Number 1 / July 1978 / Pages 91-106

Technical Paper / dx.doi.org/10.13182/NSE78-A27240

Unified Definition of a Class of Monte Carlo Estimators

Iván Lux

Nuclear Science and Engineering / Volume 67 / Number 1 / July 1978 / Pages 107-119

Technical Paper / dx.doi.org/10.13182/NSE78-A27241

Thermal-Neutron Wave Propagation in Finite Assemblies of Beryllium and Beryllium Oxide

Ashok Kumar, Feroz Ahmed, L. S. Kothari

Nuclear Science and Engineering / Volume 67 / Number 1 / July 1978 / Pages 120-129

Technical Note / dx.doi.org/10.13182/NSE78-A27242

Note on the Fast-Neutron Total Cross Section of Thorium

J. F. Whalen, A. B. Smith

Nuclear Science and Engineering / Volume 67 / Number 1 / July 1978 / Pages 129-130

Technical Note / dx.doi.org/10.13182/NSE78-A27243

Interactive Graphics Interpretation of Calculation-Measurement Discrepancies for Neutron Spectrum Measurements in Sodium

Ansar Parvez, Martin Becker

Nuclear Science and Engineering / Volume 67 / Number 1 / July 1978 / Pages 130-136

Technical Note / dx.doi.org/10.13182/NSE78-A27244

Number 2

Table of Contents
Principles of Isotope Geology(Vincent P. Guinn)
Nuclear Power Reactor Safety(David Okrent)
Heat Transfer and Turbulent Buoyant Convection: Studies and Applications for Natural Environment, Buildings, Engineering Systems(C. J. Hsu)
Reactor Neutron Cross Sections for Some (n, ã) Reactions(R. S. Tilbury, Henry H. Kramer)

Spectrum of the Multigroup-Multipoint Diffusion Operator with Delayed Neutrons

J. Devooght

Nuclear Science and Engineering / Volume 67 / Number 2 / August 1978 / Pages 147-161

Technical Paper / dx.doi.org/10.13182/NSE78-A15432

The Application of the Symmetric SOR and the Symmetric SIP Methods for the Numerical Solution of the Neutron Diffusion Equation

H. H. Wang

Nuclear Science and Engineering / Volume 67 / Number 2 / August 1978 / Pages 162-171

Technical Paper / dx.doi.org/10.13182/NSE78-A15433

Spatial Distribution Measurements of Fission Neutrons in Water as an Oxygen Data Test

L. Green, J. J. Ullo

Nuclear Science and Engineering / Volume 67 / Number 2 / August 1978 / Pages 172-183

Technical Paper / dx.doi.org/10.13182/NSE78-A15434

A Measurement of the Total Neutron Cross Section of Iron-58 in the Energy Range from 7 to 325 keV

H. Beer, Ly Di Hong, F. Käppeler

Nuclear Science and Engineering / Volume 67 / Number 2 / August 1978 / Pages 184-189

Technical Paper / dx.doi.org/10.13182/NSE78-A15435

Unified Absolute Differential Cross Sections for Neutron Production by the Hydrogen Isotopes for Charged-Particle Energies Between 6 and 17 MeV

M. Drosg

Nuclear Science and Engineering / Volume 67 / Number 2 / August 1978 / Pages 190-220

Technical Paper / dx.doi.org/10.13182/NSE67-190

Improved Resonance Formulas for Cross Sections of Fissile Elements

M. Segev

Nuclear Science and Engineering / Volume 67 / Number 2 / August 1978 / Pages 221-234

Technical Paper / dx.doi.org/10.13182/NSE78-A15437

A Computational Study of the Density and Temperature Distribution in a Freely Expanding Uranium Hexafluoride Gas

H. Mikami

Nuclear Science and Engineering / Volume 67 / Number 2 / August 1978 / Pages 235-246

Technical Paper / dx.doi.org/10.13182/NSE78-A15438

A Calculation Model for Predicting Concentrations of Radioactive Corrosion Products in the Primary Coolant of Boiling Water Reactors

Shunsuke Uchida, Makoto Kikuchi, Yamato Asakura, Hideo Yusa, Katsumi Ohsumi

Nuclear Science and Engineering / Volume 67 / Number 2 / August 1978 / Pages 247-254

Technical Paper / dx.doi.org/10.13182/NSE78-A15439

Fusion-Fission Analogy and Tnτ Criterion for Fusion Plasmas

J. Rand McNally, Jr.

Nuclear Science and Engineering / Volume 67 / Number 2 / August 1978 / Pages 255-257

Technical Note / dx.doi.org/10.13182/NSE78-A15440

Benchmark Calculations for a Sodium-Cooled Breeder Reactor by Two- and Three-Dimensional Diffusion Methods—II

G. Buckel, K. Küfner, B. Stehle

Nuclear Science and Engineering / Volume 67 / Number 2 / August 1978 / Pages 257-259

Technical Note / dx.doi.org/10.13182/NSE78-A15441

The Inverse Problem for a Finite Slab

C. E. Siewert

Nuclear Science and Engineering / Volume 67 / Number 2 / August 1978 / Pages 259-260

Technical Note / dx.doi.org/10.13182/NSE78-A15442

Precise Measurement of the ⁶³Cu(n,α)⁶⁰Co Cross Section with 14-MeV Neutrons

G. Winkler

Nuclear Science and Engineering / Volume 67 / Number 2 / August 1978 / Pages 260-263

Technical Note / dx.doi.org/10.13182/NSE78-A15443

A Quantitative Comparison of Solidification Analysis for Single-Component and Mixed-Oxide Fuels

Timothy D. Welch, August W. Cronenberg

Nuclear Science and Engineering / Volume 67 / Number 2 / August 1978 / Pages 263-269

Technical Note / dx.doi.org/10.13182/NSE78-A15444

The Volume Adsorption Capacity of 0.98 mol% Argon on Activated Carbon at 20°C

R. Madey, P. J. Photinos, K. B. Lee

Nuclear Science and Engineering / Volume 67 / Number 2 / August 1978 / Pages 269-270

Technical Note / dx.doi.org/10.13182/NSE78-A15445

Number 3

Reflectors, Infinite Cylinders, Intersecting Cylinders, and Nuclear Criticality

J. T. Thomas

Nuclear Science and Engineering / Volume 67 / Number 3 / September 1978 / Pages 279-295

Technical Paper / dx.doi.org/10.13182/NSE78-A27249

Noise Source Estimation of Boiling Water Reactor Power Fluctuation by Autoregression

Kohyu Fukunishi

Nuclear Science and Engineering / Volume 67 / Number 3 / September 1978 / Pages 296-308

Technical Paper / dx.doi.org/10.13182/NSE78-A27250

A Monte Carlo Biasing Scheme for Adjoint Photon Transport

A. De Matteis, R. Simonini

Nuclear Science and Engineering / Volume 67 / Number 3 / September 1978 / Pages 309-316

Technical Paper / dx.doi.org/10.13182/NSE78-A27251

Systematic Study of Some Standard Variance Reduction Techniques

I. Lux

Nuclear Science and Engineering / Volume 67 / Number 3 / September 1978 / Pages 317-325

Technical Paper / dx.doi.org/10.13182/NSE78-A27252

The Total Neutron Cross Section of Scandium from 0.005 to 22 keV

H. I. Liou, R. E. Chrien, R. C. Block, K. Kobayashi

Nuclear Science and Engineering / Volume 67 / Number 3 / September 1978 / Pages 326-333

Technical Paper / dx.doi.org/10.13182/NSE78-A27253

Cross-Section Measurement for the Reaction ¹¹⁵In(n,n′)^115mIn

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

Nuclear Science and Engineering / Volume 67 / Number 3 / September 1978 / Pages 334-338

Technical Paper / dx.doi.org/10.13182/NSE78-7

Comment on Particle Collision Method in Spherical Geometry by Escape Probabilities

Michael S. Milgram

Nuclear Science and Engineering / Volume 67 / Number 3 / September 1978 / Pages 339-340

Technical Note / dx.doi.org/10.13182/NSE78-A27255

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

Mahmoud Metghalchi

Nuclear Science and Engineering / Volume 67 / Number 3 / September 1978 / Pages 341-342

Technical Note / dx.doi.org/10.13182/NSE78-A27256

Neutron Attenuation due to Boron-10 Shields

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

Nuclear Science and Engineering / Volume 67 / Number 3 / September 1978 / Pages 343-344

Technical Note / dx.doi.org/10.13182/NSE78-A27257

The Dependence of the Gamma-Ray Spectral Shape on the Neutron Energy Averaging Interval Size for the ¹⁸¹Ta(n,γ) Reaction

M. Stelts, J. C. Browne

Nuclear Science and Engineering / Volume 67 / Number 3 / September 1978 / Pages 344-347

Technical Note / dx.doi.org/10.13182/NSE78-A27258

Implicit and Explicit Higher Order Perturbation Methods for Nuclear Reactor Analysis

A. Gandini

Nuclear Science and Engineering / Volume 67 / Number 3 / September 1978 / Pages 347-355

Technical Note / dx.doi.org/10.13182/NSE78-5

Further Analysis of the Zero-Energy Experiment on the Dragon Reactor

F. Woloch, W. Neuberger

Nuclear Science and Engineering / Volume 67 / Number 3 / September 1978 / Pages 355-363

Technical Note / dx.doi.org/10.13182/NSE78-A27260

Symmetrized Neutron Transport Equation and the Fast Fourier Transform Method

Nguyen Quang Sinh, Jan Kisyński, Janusz Mika

Nuclear Science and Engineering / Volume 67 / Number 3 / September 1978 / Pages 363-370

Technical Note / dx.doi.org/10.13182/NSE78-A27261