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Number 1

Table of Contents

Preconditioning the Power Method for Reactor Calculations
A. Hébert
Nuclear Science and Engineering | Volume 94 | Number 1 | September 1986 | Pages 1-11
Technical Paper | doi.org/10.13182/NSE86-A17111
Boiling Water Reactor Dynamics Identification by the Dynamic Data System Methodology
Z P. Luo, S. M. Wu
Nuclear Science and Engineering | Volume 94 | Number 1 | September 1986 | Pages 12-23
Technical Paper | doi.org/10.13182/NSE86-A17112
Validity of the Geometric-Progression Formula in Approximating Gamma-Ray Buildup Factors
Y. Harima, Y. Sakamoto, S. Tanaka, M. Kawai
Nuclear Science and Engineering | Volume 94 | Number 1 | September 1986 | Pages 24-35
Technical Paper | doi.org/10.13182/NSE86-A17113
Monte Carlo Analysis of Aqueous ²³⁵U Critical Assemblies with ENDF/B-V Data
Philip F. Rose
Nuclear Science and Engineering | Volume 94 | Number 1 | September 1986 | Pages 36-41
Technical Paper | doi.org/10.13182/NSE86-A17114
Measurements of Neutron Fission Cross Sections of ²³⁷Np, ²⁴⁰Pu, ²⁴¹Pu, ²⁴²Pu, ²⁴⁴Pu, and ²⁴¹Am at 14.7 MeV
K. Gul, M. Ahmad, M. Anwar, S. M. Saleem
Nuclear Science and Engineering | Volume 94 | Number 1 | September 1986 | Pages 42-45
Technical Paper | doi.org/10.13182/NSE86-A17115
Sensitivity Analysis Using Computer Calculus: A Nuclear Waste Isolation Application
E. M. O blow, F. G. Pin, R. Q. Wright
Nuclear Science and Engineering | Volume 94 | Number 1 | September 1986 | Pages 46-65
Technical Paper | doi.org/10.13182/NSE86-A17116
On the Excitation of Neutron Flux Waves in Reactor Core Transients
F. C. Difilippo, R. B. Perez
Nuclear Science and Engineering | Volume 94 | Number 1 | September 1986 | Pages 66-69
Technical Note | doi.org/10.13182/NSE86-A17117
A Technique for the Evaluation of Angular Integrals in Neutron Transfer Matrix Generatio
R. D. M. Garcia
Nuclear Science and Engineering | Volume 94 | Number 1 | September 1986 | Pages 70-76
Technical Note | doi.org/10.13182/NSE86-A17118
A Criterion for Predicting Thermal Stratification Due to High-Pressure Injection in a Circulating Reactor Loop
H. P. Nourbakhsh, T. G. Theofanous
Nuclear Science and Engineering | Volume 94 | Number 1 | September 1986 | Pages 77-79
Technical Note | doi.org/10.13182/NSE86-A17119
The Power-Sharing Formula for a Seed/Blanket Core — Resolution of a Paradox
A. Radkowsky, M. Segev, A. Galperin
Nuclear Science and Engineering | Volume 94 | Number 1 | September 1986 | Pages 80-86
Technical Note | doi.org/10.13182/NSE86-A17120
An Eigenvalue and Eigenfunction Study of Space-Dependent Fast Neutron Spectra in ²³²Th
Pramila Mohan, Rajesh Mohan, Feroz Ahmed, L. S. Kothari, Hiroyuki Kadotani
Nuclear Science and Engineering | Volume 94 | Number 1 | September 1986 | Pages 87-93
Technical Note | doi.org/10.13182/NSE86-A17121
Radiative Capture and (n, γn') Cross Sections for Fast Neutrons Interacting with ¹⁹⁷Au
S. Joly
Nuclear Science and Engineering | Volume 94 | Number 1 | September 1986 | Pages 94-101
Technical Note | doi.org/10.13182/NSE86-A17122
Resolved Resonance Parameters for ²³⁸U from 1 to 10 keV
D. K. Olsen
Nuclear Science and Engineering | Volume 94 | Number 1 | September 1986 | Pages 102-106
Technical Note | doi.org/10.13182/NSE86-A17123

Number 2

Table of Contents

Controlling Principles for Prior Probability Assignments in Nuclear Risk Assessment
Ian Cook, Stephen D. Unwin
Nuclear Science and Engineering | Volume 94 | Number 2 | October 1986 | Pages 107-119
Technical Paper | doi.org/10.13182/NSE86-A27446
Production of Tritium and ⁴He in a Large Cylinder of ⁶LiD Irradiated with 14-MeV Neutrons and Comparison with Monte Carlo Calculations
Eugene Goldberg, Ronald L. Barber, Norman A. Bonner, Clyde M. Griffith, David R. Nethaway, Robert C. Haight
Nuclear Science and Engineering | Volume 94 | Number 2 | October 1986 | Pages 120-135
Technical Paper | doi.org/10.13182/NSE86-A27447
Helium Production Cross Sections for 15-MeV Neutrons on ⁶Li and ⁷Li
D. W. Kneff, B. M. Oliver, E. Goldberg, R. C. Haight
Nuclear Science and Engineering | Volume 94 | Number 2 | October 1986 | Pages 136-144
Technical Paper | doi.org/10.13182/NSE86-A27448
Application of Adaptive Control to a Nuclear Power Plant
Gwi Tae Park, George H. Miley
Nuclear Science and Engineering | Volume 94 | Number 2 | October 1986 | Pages 145-156
Technical Paper | doi.org/10.13182/NSE86-A27449
A Flux-Limited Diffusion Model for Charged-Particle Transport
M. R. Dorr, J. F. Painter, S. T. Perkins
Nuclear Science and Engineering | Volume 94 | Number 2 | October 1986 | Pages 157-166
Technical Paper | doi.org/10.13182/NSE86-A27450
Two-Fluid Model Simulation of Density-Wave Oscillations in a Boiling Flow System
R. C. Dykhuizen, R. P. Roy, S. P. Kalra
Nuclear Science and Engineering | Volume 94 | Number 2 | October 1986 | Pages 167-179
Technical Paper | doi.org/10.13182/NSE86-A27451
Application of an Automated Procedure for Adding a Comprehensive Sensitivity Calculation Capability to the ORIGEN2 Point Depletion and Radioactive Decay Code
B. A. Worley, R. Q. Wright, F. G. Pin, W. V. Harper
Nuclear Science and Engineering | Volume 94 | Number 2 | October 1986 | Pages 180-191
Technical Paper | doi.org/10.13182/NSE86-A27452
Carbon Kerma Factor for 18- and 20-MeV Neutrons
P. M. DeLuca, Jr., H. H. Barschall, M. Burhoe, R. C. Haight
Nuclear Science and Engineering | Volume 94 | Number 2 | October 1986 | Pages 192-198
Technical Note | doi.org/10.13182/NSE86-A27453
An Interpolation Method for Functions of Two Variables with Applications to Radiation Measurements
Hsiao-Hua Hsu
Nuclear Science and Engineering | Volume 94 | Number 2 | October 1986 | Pages 199-205
Technical Note | doi.org/10.13182/NSE86-A27454
Some Theoretical Investigations on Prompt Self-Powered Neutron Detectors (Hafnium and Erbium Emitters)
N. A. Antonov, Y. D. Yordanov
Nuclear Science and Engineering | Volume 94 | Number 2 | October 1986 | Pages 206-212
Technical Note | doi.org/10.13182/NSE86-A27455

Number 3

Table of Contents
Comments on “Application of Neutron Transport Green's Functions to the Calculation of Pressure Vessel Fluence” (K. Shure)
Response to “Comments on ‘The Nonlinear Dynamics of the Oklo Natural Reactor’” (Archie A. Harms)
Comments on “The Nonlinear Dynamics of the Oklo Natural Reactor” (David L. Hetrick)
Monte Carlo Simulation of the Gamma Dose Rate in a Loss-of-Water Accident at the North Carolina State University Research Reactor (J. M. Doster, B. E. Hey)

A Methodology for Analyzing the Detection and Suppression of Fires in Nuclear Power Plants
Nathan Siu, George Apostolakis
Nuclear Science and Engineering | Volume 94 | Number 3 | November 1986 | Pages 213-226
Technical Paper | doi.org/10.13182/NSE86-A17264
Absolute Measurements of the ¹¹⁵In(n,γ)^116m₁In Cross Section for Fast Neutrons
D. J. Grady, G. F. Knoll, J. C. Robertson
Nuclear Science and Engineering | Volume 94 | Number 3 | November 1986 | Pages 227-232
Technical Paper | doi.org/10.13182/NSE86-A17265
Incorporation of Monte Carlo Electron Interface Studies into Photon General Cavity Theory
Y. S. Horowitz, M. Moscovitch, J. M. Mack, H. Hsu, E. Kearsley
Nuclear Science and Engineering | Volume 94 | Number 3 | November 1986 | Pages 233-240
Technical Paper | doi.org/10.13182/NSE86-A17266
Explicit Burnable Absorber Modeling for Pressurized Water Reactor Core Reload Design Applications
T. J. Downar, J. A. Stillman
Nuclear Science and Engineering | Volume 94 | Number 3 | November 1986 | Pages 241-250
Technical Paper | doi.org/10.13182/NSE86-A17267
Neutron Diffusion in Spheroidal, Bispherical, and Toroidal Systems
M. M. R. Williams
Nuclear Science and Engineering | Volume 94 | Number 3 | November 1986 | Pages 251-263
Technical Paper | doi.org/10.13182/NSE86-A17268
On Two-Group Critical Problems in Neutron-Transport Theory
C. E. Siewert, J. R. Thomas, Jr.
Nuclear Science and Engineering | Volume 94 | Number 3 | November 1986 | Pages 264-270
Technical Paper | doi.org/10.13182/NSE86-A17269
Approximate Solution to the Kolmogorov Equation for a Fission Chain-Reacting System
Lawrence Ruby, Thomas L. McSwine
Nuclear Science and Engineering | Volume 94 | Number 3 | November 1986 | Pages 271-273
Technical Note | doi.org/10.13182/NSE86-A17270
Choice of Biasing Function for Source Biasing
Ely M. Gelbard
Nuclear Science and Engineering | Volume 94 | Number 3 | November 1986 | Pages 274-276
Technical Note | doi.org/10.13182/NSE86-A17271
Spectral Covariance Associated with the Monte Carlo Method
Hiroshi Sekimoto
Nuclear Science and Engineering | Volume 94 | Number 3 | November 1986 | Pages 277-281
Technical Note | doi.org/10.13182/NSE86-A17272
Radiation Safety Considerations for a Test of Deep Geologic Storage of Spent Nuclear Fuel
K. Raschke, T. Straume
Nuclear Science and Engineering | Volume 94 | Number 3 | November 1986 | Pages 282-286
Technical Note | doi.org/10.13182/NSE86-A17273

Number 4

Table of Contents
A Short Table of Indefinite Integrals of the Exponential Integral Function (Norman G. Gunther)
On the Derivation of the Equations of the Point-Reactor Model (J. Pantuso Sudano)

Accounting for Changing Source Distributions in Light Water Reactor Surveillance Dosimetry Analysis
R. E. Maerker, M. L. Williams, B. L. Broadhead
Nuclear Science and Engineering | Volume 94 | Number 4 | December 1986 | Pages 291-308
Technical Paper | doi.org/10.13182/NSE86-A18342
A Linear Discontinuous Finite Difference Formulation for Synthetic Coarse-Mesh Few-Group Diffusion Calculations
José M. Aragonés, Carol Ahnert
Nuclear Science and Engineering | Volume 94 | Number 4 | December 1986 | Pages 309-322
Technical Paper | doi.org/10.13182/NSE86-A18343
Variance Reduction Under Exponential and Scattering Angle Biasing: An Analytic Approach
R. Indira, T. M. John
Nuclear Science and Engineering | Volume 94 | Number 4 | December 1986 | Pages 323-336
Technical Paper | doi.org/10.13182/NSE86-A18344
Independent Fission Yield Measurements
Hans Otto Denschlag
Nuclear Science and Engineering | Volume 94 | Number 4 | December 1986 | Pages 337-352
Technical Paper | doi.org/10.13182/NSE86-A18345
Composite Delayed Neutron Energy Spectra for Thermal Fission of ²³⁵U
R. S. Tanczyn, Q. Sharfuddin, W. A. Schier, D. J. Pullen, M. H. Haghighi, L. Fisteag, and G. P. Couchell
Nuclear Science and Engineering | Volume 94 | Number 4 | December 1986 | Pages 353-364
Technical Paper | doi.org/10.13182/NSE86-A18346
Measurements of the Energy Dependence of Prompt Neutron Emission from ²³³U, ²³⁵U, and ²³⁹Pu for E_n = 0.0005 to 10 MeV Relative to Emission from Spontaneous Fission of ²⁵²Cf
R. Gwin, R. R. Spencer, R. W. Ingle
Nuclear Science and Engineering | Volume 94 | Number 4 | December 1986 | Pages 365-379
Technical Paper | doi.org/10.13182/NSE86-A18347
Higher Order Perturbation Theory — An Example for Discussion
J. D. Lewins, G. Parks, A. L. Babb
Nuclear Science and Engineering | Volume 94 | Number 4 | December 1986 | Pages 380-392
Technical Paper | doi.org/10.13182/NSE86-A18348
Calculation of the Neutron Flux in a Heterogeneous Reactor Polycell with Fuel Multirod Clusters in a One-Group P₃ Approximation
V. E. Raevskaya
Nuclear Science and Engineering | Volume 94 | Number 4 | December 1986 | Pages 393-408
Technical Paper | doi.org/10.13182/NSE86-A18349
Direct and Indirect Computation of the Transport Equation Eigenvalues
R. L. Perel, J.J. Wagschal
Nuclear Science and Engineering | Volume 94 | Number 4 | December 1986 | Pages 409-412
Technical Note | doi.org/10.13182/NSE94-409
Mass Distribution in the Fission of ²³²Th by Degraded-Fission-Spectrum Neutrons
Albert E. Richardson, Harold L. Wright, John L. Meason, James R. Smith
Nuclear Science and Engineering | Volume 94 | Number 4 | December 1986 | Pages 413-425
Technical Note | doi.org/10.13182/NSE86-A18351