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Volume 114

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Number 1

Table of Contents
The P_N Theory as an Asymptotic Limit of Transport Theory in Planar Geometry—I: Analysis(Edward W. Larsen and G. C. Pomraning)

Investigation of Radiation Effects in Hiroshima and Nagasaki Using a General Monte Carlo-Discrete Ordinates Coupling Scheme

S. N. Cramer, C. O. Slater

Nuclear Science and Engineering / Volume 114 / Number 1 / May 1993 / Pages 1-11

Technical Paper / dx.doi.org/10.13182/NSE93-A24009

Asymptotically Exact Boundary Conditions for the P_N Equations

B. D. Ganapol, C. T. Kelley, G. C. Pomraning

Nuclear Science and Engineering / Volume 114 / Number 1 / May 1993 / Pages 12-19

Technical Paper / dx.doi.org/10.13182/NSE93-A24010

An Upwind Nodal Integral Method for Incompressible Fluid Flow

Peter D. Esser, Robert J. Witt

Nuclear Science and Engineering / Volume 114 / Number 1 / May 1993 / Pages 20-35

Technical Paper / dx.doi.org/10.13182/NSE93-A24011

The Combination of Data and Functional Partitioning to Parallelize Severe Accident Computer Codes

Timothy J. Tautges, Gregory A. Moses, Michael L. Corradini

Nuclear Science and Engineering / Volume 114 / Number 1 / May 1993 / Pages 36-41

Technical Paper / dx.doi.org/10.13182/NSE93-A24012

Safety Control of Nuclear Power Operations Using Self-Programming Neural Networks

Wayne C. Jouse, John G. Williams

Nuclear Science and Engineering / Volume 114 / Number 1 / May 1993 / Pages 42-54

Technical Paper / dx.doi.org/10.13182/NSE93-A24013

A Unified Hauser-Feshbach and Exciton Model for Calculating Double-Differential Cross Sections of Neutron-Induced Reactions Below 20 MeV

Jingshang Zhang

Nuclear Science and Engineering / Volume 114 / Number 1 / May 1993 / Pages 55-63

Technical Paper / dx.doi.org/10.13182/NSE93-3

A Combined Cross-Section Adjustment and Bias Factor Method for Accurate Prediction of Fast Breeder Reactor Core Performance Parameters

Toshikazu Takeda, Kazuhisa Matsumoto

Nuclear Science and Engineering / Volume 114 / Number 1 / May 1993 / Pages 64-75

Technical Paper / dx.doi.org/10.13182/NSE93-A24015

Absorbed-Dose Buildup Factors in Air for 10- to 100-MeV Photons

Richard E. Faw, J. Kenneth Shultis

Nuclear Science and Engineering / Volume 114 / Number 1 / May 1993 / Pages 76-80

Technical Notes / dx.doi.org/10.13182/NSE93-A24016

Verification of the CASAAO-3/SIMULATE-3 Pin Power Accuracy by Comparison with Operating Boiling Water Reactor Measurements

T. Uegata, E. Saji, H. Tanaka

Nuclear Science and Engineering / Volume 114 / Number 1 / May 1993 / Pages 81-85

Technical Notes / dx.doi.org/10.13182/NSE93-A24017

Number 2

Table of Contents
The HEXAB-3D Three-Dimensional Few-Group Improved Coarse-Mesh Diffusion Code for Hexagonal-z Geometry(K. N. Ivanov, T. G. Apostolov, M. A. Manolova)

A Burnup-Compensated Madland-Nix Prompt Fission Neutron Source Term for Multigroup Nuclear Reactor Shielding Calculations

T. J. van Rooyen, G. P. de Beer

Nuclear Science and Engineering / Volume 114 / Number 2 / June 1993 / Pages 87-101

Technical Paper / dx.doi.org/10.13182/NSE93-A24020

A Model for Fission Product Release from Liquid-Metal Pools: Development and Sensitivity Investigation

P. R. McClure, M. T. Leonard, A. Razani

Nuclear Science and Engineering / Volume 114 / Number 2 / June 1993 / Pages 102-111

Technical Paper / dx.doi.org/10.13182/NSE93-A24021

Neutron Spectrum Measurements of a Thorium Dioxide Assembly

Paul S. Feigenbaum, Martin Becker, Donald R. Harris Bimal K. Malaviya, Robert C. Block, S. A. Hayashi, S. Yamamoto

Nuclear Science and Engineering / Volume 114 / Number 2 / June 1993 / Pages 112-117

Technical Paper / dx.doi.org/10.13182/NSE93-A24022

Calculation of Recoil Ion Effective Track Lengths in Neutron-Radiation-Induced Nucleation

Mark J. Harper

Nuclear Science and Engineering / Volume 114 / Number 2 / June 1993 / Pages 118-123

Technical Paper / dx.doi.org/10.13182/NSE93-A24023

Calculation of Neutron Superinelastic Scattering in ^178mHf

G. Reffo and M. H. MacGregor

Nuclear Science and Engineering / Volume 114 / Number 2 / June 1993 / Pages 124-134

Technical Paper / dx.doi.org/10.13182/NSE93-A24024

Condensation on Nonspherical Aerosol Particles: Numerical Solutions in the Continuum Regime

S. K. Loyalka, J. L. Griffin

Nuclear Science and Engineering / Volume 114 / Number 2 / June 1993 / Pages 135-140

Technical Paper / dx.doi.org/10.13182/NSE93-A24025

Sensor Fault Detection with the Single Sensor Parity Relation

T. M. Tsai , H. P. Chou

Nuclear Science and Engineering / Volume 114 / Number 2 / June 1993 / Pages 141-148

Technical Paper / dx.doi.org/10.13182/NSE93-A24026

Measurements and Calculations of Radionuclides Created by ¹⁸¹Ta(γ,xn yp) Reactions for Bremsstrahlung Photons Produced by 150-MeV Electrons

J. K. Dickens , M. A. Miller

Nuclear Science and Engineering / Volume 114 / Number 2 / June 1993 / Pages 149-159

Technical Note / dx.doi.org/10.13182/NSE93-A24027

Analysis of ONEDANT Code Package for the Calculation of the Doppler Coefficient of Reactivity

I. Soares, W. F. Miller, Jr., R. T. Perry

Nuclear Science and Engineering / Volume 114 / Number 2 / June 1993 / Pages 160-167

Technical Note / dx.doi.org/10.13182/NSE93-A24028

Derivation of Anisotropic Diffusion Coefficients in a Large Annular Cavity

Eiichi Suetomi, Hiroshi Sekimoto

Nuclear Science and Engineering / Volume 114 / Number 2 / June 1993 / Pages 168-175

Technical Note / dx.doi.org/10.13182/NSE93-A24029

Number 3

Table of Contents

The Vibration Behavior of Nuclear Fuel Under Reactor Conditions

M. J. Pettigrew

Nuclear Science and Engineering / Volume 114 / Number 3 / July 1993 / Pages 179-189

Technical Paper / dx.doi.org/10.13182/NSE93-A24032

Photoneutron Production Using Bremsstrahlung from the 14-TW Pulsed-Power HERMES III Electron Accelerator

T. W. L. Sanford, L. J. Lorence, J. A. Halbleib, J. G. Kelly, P. J. Griffin, J. W. Poukey, W. H. McAtee, R. C. Mock

Nuclear Science and Engineering / Volume 114 / Number 3 / July 1993 / Pages 190-213

Technical Paper / dx.doi.org/10.13182/NSE93-A24033

Transmitted Photon Spectra of Gamma Rays Through a Soil Medium

Makhan Singh, G. S. Brar, Gurmel S. Mudahar

Nuclear Science and Engineering / Volume 114 / Number 3 / July 1993 / Pages 214-218

Technical Paper / dx.doi.org/10.13182/NSE93-A24034

Benchmarking the MCNP Monte Carlo Code with a Photon Skyshine Experiment

Richard H. Olsher, Hsiao-Hua Hsu, Wells F. Harvey

Nuclear Science and Engineering / Volume 114 / Number 3 / July 1993 / Pages 219-227

Technical Paper / dx.doi.org/10.13182/NSE93-A24035

Use of Monte Carlo Procedures to Estimate First and Second Collision Sources for Discrete Ordinates Transport Codes

L. M. Gomes, P. N. Stevens

Nuclear Science and Engineering / Volume 114 / Number 3 / July 1993 / Pages 228-237

Technical Paper / dx.doi.org/10.13182/NSE93-A24036

Optimal Flux Map Generation Through Parameter Estimation Techniques

James W. Bryson, John C. Lee, Jeré A. Hassberger

Nuclear Science and Engineering / Volume 114 / Number 3 / July 1993 / Pages 238-251

Technical Paper / dx.doi.org/10.13182/NSE93-A24037

Parallel Solution of the Neutron Diffusion Equation with the Domain Decomposition Method on a Transputer Network

Yong Hee Kim, Nam Zin Cho

Nuclear Science and Engineering / Volume 114 / Number 3 / July 1993 / Pages 252-270

Technical Paper / dx.doi.org/10.13182/NSE93-A24038

Number 4

Table of Contents
U.S. Spent-Fuel Disposal Strategies and International Safeguards(K. K. S. Pillay, R. R. Picard, J. F. Hafer)
Comment on "Analysis of Cluster Geometries Using the DP1 Approximation of the J_± Technique"(P. Mohanakrishnan)

Variational Derivation and Numerical Analysis of P₂ Theory in Planar Geometry

Robert P. Rulko, Edward W. Larsen

Nuclear Science and Engineering / Volume 114 / Number 4 / August 1993 / Pages 271-285

Technical Paper / dx.doi.org/10.13182/NSE93-A24040

Uncertainty and Sensitivity Analysis Results Obtained in a Preliminary Performance Assessment for the Waste Isolation Pilot Plant

J. C. Helton, J. W. Garner, M. G. Marietta, R. P. Rechard, D. K. Rudeen, P. N. Swift

Nuclear Science and Engineering / Volume 114 / Number 4 / August 1993 / Pages 286-331

Technical Paper / dx.doi.org/10.13182/NSE93-A24041

The Effective Beta Sensitivity to the Incident Neutron Energy Dependence of the Absolute Delayed Neutron Yields

A. D’Angelo,A. Filip

Nuclear Science and Engineering / Volume 114 / Number 4 / August 1993 / Pages 332-341

Technical Paper / dx.doi.org/10.13182/NSE93-A24042

In-Pile Measurement of the Decay Constants and Relative Abundances of Delayed Neutrons

Gregory D. Spriggs

Nuclear Science and Engineering / Volume 114 / Number 4 / August 1993 / Pages 342-351

Technical Paper / dx.doi.org/10.13182/NSE92-78

A Relative Measurement of the ¹⁰B(n,α₁γ)⁷Li Cross Section Between 0.2 and 4.0 MeV

R. A. Schrack, O. A. Wasson,D. C. Larson, J. K. Dickens, J. H. Todd

Nuclear Science and Engineering / Volume 114 / Number 4 / August 1993 / Pages 352-362

Technical Paper / dx.doi.org/10.13182/NSE93-A24044