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Number 1
Number 2

Number 3

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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NSE78-A27244

Number 2

Table of Contents
Nuclear Power Reactor Safety (David Okrent)
Principles of Isotope Geology (Vincent P. Guinn)
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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NSE78-A27261