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Volume 113

Number 1 | Number 2 | Number 3 | Number 4

Number 1

Table of Contents
On “Simultaneous Estimation of Neutron Density and Reactivity in a Nuclear Reactor Using a Bank of Kalman Filters”(Attila Rácz)
Reply to “On ‘Simultaneous Estimation of Neutron Density and Reactivity in a Nuclear Reactor Using a Bank of Kalman Filters’ ”(Carlos E. D’Attellis)

Laboratory Measurement of the Heat Capacity of Urania up to 8000 K: I. Experiment

C. Ronchi, J. P. Hiernaut, R. Selfslag, G. J. Hyland

Nuclear Science and Engineering / Volume 113 / Number 1 / January 1993 / Pages 1-19

Technical Paper / dx.doi.org/10.13182/NSE93-A23990

Heavy Nucleus Resonant Absorption Calculation Benchmarks

H. Tellier, M. Coste, C. Raepsaet, C. Van der Gucht

Nuclear Science and Engineering / Volume 113 / Number 1 / January 1993 / Pages 20-30

Technical Paper / dx.doi.org/10.13182/NSE93-A23991

Langevin Equation Approach to Reactor Noise Analysis: Stochastic Transport Equation

A. Ziya Akcasu, Alison M. Stolle

Nuclear Science and Engineering / Volume 113 / Number 1 / January 1993 / Pages 31-55

Technical Paper / dx.doi.org/10.13182/NSE93-A23992

A Stochastic Cellular Automata Model for Neutron Transport

Michael J. Gaeta, Bahram Nassersharif

Nuclear Science and Engineering / Volume 113 / Number 1 / January 1993 / Pages 56-69

Technical Paper / dx.doi.org/10.13182/NSE93-A23993

Pressurized Water Reactor Core Parameter Prediction Using an Artificial Neural Network

Han Gon Kim, Soon Heung Chang, Byung Ho Lee

Nuclear Science and Engineering / Volume 113 / Number 1 / January 1993 / Pages 70-76

Technical Paper / dx.doi.org/10.13182/NSE93-A23994

A Test of MCNP with a ⁶Li-Glass Moderating Neutron Detector

J. C. Wang, Gary L. Jensen, J. B. Czirr

Nuclear Science and Engineering / Volume 113 / Number 1 / January 1993 / Pages 77-85

Technical Paper / dx.doi.org/10.13182/NSE93-A23995

Multigroup Antiproton Transport and Fission

B. R. Wienke, R. E. Seamon, D. G. Madland

Nuclear Science and Engineering / Volume 113 / Number 1 / January 1993 / Pages 86-92

Technical Note / dx.doi.org/10.13182/NSE93-A23996

Number 2

Table of Contents

Neutronic Decoupling and Space-Dependent Nuclear Characteristics for Large Liquid-Metal Fast Breeder Reactor Cores

Toshio Sanda, Fumiaki Nakashima, Keisho Shirakata

Nuclear Science and Engineering / Volume 113 / Number 2 / February 1993 / Pages 97-108

Technical Paper / dx.doi.org/10.13182/NSE113-97

Study of Compact Fast Reactor Core Designs

Tehsin Hamid, K. O. Ott

Nuclear Science and Engineering / Volume 113 / Number 2 / February 1993 / Pages 109-121

Technical Paper / dx.doi.org/10.13182/NSE93-A24001

A Fast Reactor Transient Analysis Methodology for Personal Computers

K. O. Ott

Nuclear Science and Engineering / Volume 113 / Number 2 / February 1993 / Pages 122-135

Technical Paper / dx.doi.org/10.13182/NSE93-A24002

Path Length Differencing and Energy Conservation of the S_N Boltzmann/Spencer-Lewis Equation

W. L. Filippone, S. P. Monahan

Nuclear Science and Engineering / Volume 113 / Number 2 / February 1993 / Pages 136-144

Technical Paper / dx.doi.org/10.13182/NSE93-A24003

Reactor Noise Analysis Based on Nonlinear Dynamic Theory — Application to Power Oscillation

Tomoaki Suzudo

Nuclear Science and Engineering / Volume 113 / Number 2 / February 1993 / Pages 145-160

Technical Paper / dx.doi.org/10.13182/NSE93-A24004

Two Rossi-α Techniques for Measuring the Effective Delayed Neutron Fraction

Gregory D. Spriggs

Nuclear Science and Engineering / Volume 113 / Number 2 / February 1993 / Pages 161-172

Technical Paper / dx.doi.org/10.13182/NSE93-2

Analysis of Tritium Production in a Sphere of ⁶LiD with Oralloy Core Irradiated by 14-MeV Neutrons

L. R. Fawcett, Jr.

Nuclear Science and Engineering / Volume 113 / Number 2 / February 1993 / Pages 173-183

Technical Paper / dx.doi.org/10.13182/NSE93-A24006

Neutron Production in Heavy-lon Reactions at 35 and 50 MeV/Nucleon

H. R. Schelin, A. Galonsky, C. K. Gelbke, H. Hama, L. Heilbronn, D. Krofcheck, W. G. Lynch, D. Sackett, M. B. Tsang, X. Yang, F. Deák, Á. Horvath, Á. Kiss, Z. Seres, J. Kasagi, T. Murakami

Nuclear Science and Engineering / Volume 113 / Number 2 / February 1993 / Pages 184-188

Technical Paper / dx.doi.org/10.13182/NSE93-A24007

Number 3

Table of Contents

Transient Gas Motion in Nuclear-Reactor-Pumped Lasers: Computational and Experimental Results

J. R. Torczynski, D.R. Neal

Nuclear Science and Engineering / Volume 113 / Number 3 / March 1993 / Pages 189-206

Technical Paper / dx.doi.org/10.13182/NSE93-A24488

Solubility of Nickel and Cobalt Oxides in High-Temperature Water

Kostadin Dinov, Chihiro Matsuura, Daisuke Hiroishi, Kenkichi Ishigure

Nuclear Science and Engineering / Volume 113 / Number 3 / March 1993 / Pages 207-216

Technical Paper / dx.doi.org/10.13182/NSE92-36

Thermal and Epithermal Sensitivities of Cobalt Self-Powered Neutron Detectors

Maria do Carmo Lopes, Jorge Molina Avila

Nuclear Science and Engineering / Volume 113 / Number 3 / March 1993 / Pages 217-226

Technical Paper / dx.doi.org/10.13182/NSE93-A24490

A Consistent Technique for the Pin-by-Pin Homogenization of a Pressurized Water Reactor Assembly

A. Hébert

Nuclear Science and Engineering / Volume 113 / Number 3 / March 1993 / Pages 227-238

Technical Paper / dx.doi.org/10.13182/NSE92-10

Criticality Analysis of Heterogeneous Light Water Reactor Configurations

S. Sitaraman, F. Rahnema

Nuclear Science and Engineering / Volume 113 / Number 3 / March 1993 / Pages 239-250

Technical Paper / dx.doi.org/10.13182/NSE93-A24492

Stability Analysis of a Linear Reactor System with Feedback Under Low-Flow, Low-Power Conditions

E. V. Depiante

Nuclear Science and Engineering / Volume 113 / Number 3 / March 1993 / Pages 251-263

Technical Paper / dx.doi.org/10.13182/NSE93-A24493

An Efficient Computational Technique for Thermal Reactor Transients

B. O. Cho, A. H. Robinson

Nuclear Science and Engineering / Volume 113 / Number 3 / March 1993 / Pages 264-270

Technical Paper / dx.doi.org/10.13182/NSE93-A24494

Application of Galerkin’s Method to Calculate the Behavior of Boiling Water Reactors During Limit-Cycle Oscillations

B.Damiano,J. A. March-Leuba

Nuclear Science and Engineering / Volume 113 / Number 3 / March 1993 / Pages 271-281

Technical Note / dx.doi.org/10.13182/NSE93-A24495

A Practical Algorithm to Derive the (α,n) Source Term in a Composite Mixture Containing Actinides

Ian R. Terry

Nuclear Science and Engineering / Volume 113 / Number 3 / March 1993 / Pages 282-285

Technical Note / dx.doi.org/10.13182/NSE93-A24496

Number 4

Table of Contents

Thermohydraulic Behavior of the Liquid-Metal Natural-Circulation Target of the Spallation Neutron Source at Paul Scherrer Institute

Y. Takeda, W. E. Fischer

Nuclear Science and Engineering / Volume 113 / Number 4 / April 1993 / Pages 287-299

Technical Paper / dx.doi.org/10.13182/NSE93-A15329

Suppression of Vapor Explosions by Dilute Aqueous Polymer Solutions

M. F. Dowling, B. M. Ip, S. I. Abdel-Khalik

Nuclear Science and Engineering / Volume 113 / Number 4 / April 1993 / Pages 300-313

Technical Paper / dx.doi.org/10.13182/NSE93-A15330

Creating and Using a Type of Free-Form Geometry in Monte Carlo Particle Transport

Daniel E. Wessol, Floyd J. Wheeler

Nuclear Science and Engineering / Volume 113 / Number 4 / April 1993 / Pages 314-323

Technical Paper / dx.doi.org/10.13182/NSE93-A15331

Quantifying the Reliability of Uncertainty Predictions in Monte Carlo Fast Reactor Physics Calculations

L. L. Carter, T. L. Miles, S. E. Binney

Nuclear Science and Engineering / Volume 113 / Number 4 / April 1993 / Pages 324-338

Technical Paper / dx.doi.org/10.13182/NSE93-A15332

A New Approach and Computational Algorithm for Sensitivity/Uncertainty Analysis for SED and SAD with Application to Beryllium Integral Experiments

Peter M. Song, Mahmoud Z. Youssef, Mohamed A. Abdou

Nuclear Science and Engineering / Volume 113 / Number 4 / April 1993 / Pages 339-366

Technical Paper / dx.doi.org/10.13182/NSE93-A15333

Detailed Behavior of Exposure Buildup Factor in Stratified Shields for Plane-Normal and Point Isotropic Sources, Including the Effects of Bremsstrahlung and Fluorescent Radiation

Yoshiko Harima, Hideo Hirayama

Nuclear Science and Engineering / Volume 113 / Number 4 / April 1993 / Pages 367-378

Technical Paper / dx.doi.org/10.13182/NSE92-52