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Volume 94

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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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NSE86-A27455

Number 3

Table of Contents
Comments on “The Nonlinear Dynamics of the Oklo Natural Reactor”(David L. Hetrick)
Response to “Comments on ‘The Nonlinear Dynamics of the Oklo Natural Reactor’”(Archie A. Harms)
Comments on “Application of Neutron Transport Green's Functions to the Calculation of Pressure Vessel Fluence”(K. Shure)
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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NSE86-A18351