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Number 1

Table of Contents

Linear Transport in Correlated Stochastic Media
J. Devooght
Nuclear Science and Engineering | Volume 124 | Number 1 | September 1996 | Pages 1-17
Technical Paper | doi.org/10.13182/NSE96-A24220
The Effectiveness of P₂ and Simplified P₂ Synthetic Accelerations in the Solutions of Discrete Ordinates Transport Equations
Taewan Noh, Warren F. Miller, Jr.
Nuclear Science and Engineering | Volume 124 | Number 1 | September 1996 | Pages 18-30
Technical Paper | doi.org/10.13182/NSE96-A24221
Analysis of Inherent Oscillations in Multidimensional S_N Solutions of the Neutron Transport Equation
Bojan G. Petrović, Alireza Haghighat
Nuclear Science and Engineering | Volume 124 | Number 1 | September 1996 | Pages 31-62
Technical Paper | doi.org/10.13182/NSE96-A24222
Discrete Transport Model Eigenfunctions
T. A. Germogenova
Nuclear Science and Engineering | Volume 124 | Number 1 | September 1996 | Pages 63-71
Technical Paper | doi.org/10.13182/NSE96-A24223
A Diffusion-Accelerated Solution Method for the Nonlinear Characteristic Scheme in Slab Geometry
Todd A. Wareing, Wallace F. Walters, Jim E. Morel
Nuclear Science and Engineering | Volume 124 | Number 1 | September 1996 | Pages 72-81
Technical Paper | doi.org/10.13182/NSE96-A24224
Accounting for Strong Localized Heterogeneities and Local Transport Effect in Core Calculation
J. M. Ruggieri, R. Boyer, J. Y. Doriath, P. J. Finck
Nuclear Science and Engineering | Volume 124 | Number 1 | September 1996 | Pages 82-88
Technical Paper | doi.org/10.13182/NSE96-A24225
Particle Transport in the Presence of Parametric Noise
Anil K. Prinja, Alejandro Gonzalez-Aller
Nuclear Science and Engineering | Volume 124 | Number 1 | September 1996 | Pages 89-96
Technical Paper | doi.org/10.13182/NSE124-89
Efficient Higher Order Nodal Finite Element Formulations for Neutron Multigroup Diffusion Equations
J. P. Hennart, E. M. Malambu, E. H. Mund
Nuclear Science and Engineering | Volume 124 | Number 1 | September 1996 | Pages 97-110
Technical Paper | doi.org/10.13182/NSE96-A24227
Methods and Performance of the Three-Dimensional Pressurized Water Reactor Core Dynamics SIMTRAN On-Line Code
José M. Aragonés, Carol Ahnert, Oscar Cabellos
Nuclear Science and Engineering | Volume 124 | Number 1 | September 1996 | Pages 111-124
Technical Paper | doi.org/10.13182/NSE96-A24228
Numerical Stability of the Six-Equation, Single-Pressure Model with Viscous Terms
J. Michael Doster, Mark A. Holmes
Nuclear Science and Engineering | Volume 124 | Number 1 | September 1996 | Pages 125-144
Technical Paper | doi.org/10.13182/NSE96-A24229
A Parallel Multigrid Preconditioned Conjugate Gradient Algorithm for Groundwater Flow Simulations
Steven F. Ashby, Robert D. Falgout
Nuclear Science and Engineering | Volume 124 | Number 1 | September 1996 | Pages 145-159
Technical Paper | doi.org/10.13182/NSE96-A24230
Incorporation of a New Spectral History Correction Method into Local Power Reconstruction for Nodal Methods
C. H. Lee, Y. J. Kim, J. W. Song, C. O. Park
Nuclear Science and Engineering | Volume 124 | Number 1 | September 1996 | Pages 160-166
Technical Paper | doi.org/10.13182/NSE96-A24231
On the Neutron Noise Diagnostics of Pressurized Water Reactor Control Rod Vibrations —IV: Application of Neural Networks
I. Pázsit, N. S. Garis, O. Glöckler
Nuclear Science and Engineering | Volume 124 | Number 1 | September 1996 | Pages 167-177
Technical Paper | doi.org/10.13182/NSE96-A24232
Multiobjective Pressurized Water Reactor Reload Core Design by Nondominated Genetic Algorithm Search
G. T. Parks
Nuclear Science and Engineering | Volume 124 | Number 1 | September 1996 | Pages 178-187
Technical Paper | doi.org/10.13182/NSE96-A24233
Fuel Management Optimization Using Genetic Algorithms and Expert Knowledge
Michael D. DeChaine, Madeline A. Feltus
Nuclear Science and Engineering | Volume 124 | Number 1 | September 1996 | Pages 188-196
Technical Paper | doi.org/10.13182/NSE96-A24234
Monte Carlo Calculation of Point-Detector Sensitivities to Material Parameters
R. L. Perel, J. J. Wagschal, Y. Yeivin
Nuclear Science and Engineering | Volume 124 | Number 1 | September 1996 | Pages 197-209
Technical Paper | doi.org/10.13182/NSE96-A24235

Number 2

Table of Contents
Comment on “Response Matrix Properties and Convergence Implications for an Interface-Current Nodal Formulation” (Mihaly Makai)
On “Neutron Fluence at the Pressure Vessel of a Pressurized Water Reactor Determined by the MCNP Code” (Alireza (Ali) Haghighat)
Reply to “On ‘Neutron Fluence at the Pressure Vessel of a Pressurized Water Reactor Determined by the MCNP Code” (Peter Laky, Nicholas Tsoulfanidis)

Solubility of Nickel Ferrite in High-Temperature Pure or Oxygenated Water
Yukiko Hanzawa, Daisuke Hiroishi, Chihiro Matsuura, Kenkichi Ishigure
Nuclear Science and Engineering | Volume 124 | Number 2 | October 1996 | Pages 211-218
Technical Paper | doi.org/10.13182/NSE96-A28572
Helium Production by 9.85-MeV Neutrons in Elemental Iron, Nickel, and Copper and in ⁵⁶Fe and ^58,60,61ni
R. C. Haight, D. W. Kneff, B. M. Oliver, L. R. Greenwood, H. Vonach
Nuclear Science and Engineering | Volume 124 | Number 2 | October 1996 | Pages 219-227
Technical Paper | doi.org/10.13182/NSE96-A28573
Transmission Through Shields of Quasi-Monoenergetic Neutrons Generated by 43- and 68-MeV Protons —I: Concrete Shielding Experiment and Calculation for Practical Application
Noriaki Nakao, Hiroshi Nakashima, Takashi Nakamura, Shun-ichi Tanaka, Susumu Tanaka, Kazuo Shin, Mamoru Baba, Yukio Sakamoto, Yoshihiro Nakane
Nuclear Science and Engineering | Volume 124 | Number 2 | October 1996 | Pages 228-242
Technical Paper | doi.org/10.13182/NSE96-A28574
Transmission Through Shields of Quasi-Monoenergetic Neutrons Generated by 43- and 68-MeV Protons —II: Iron Shielding Experiment and Analysis for Investigating Calculational Method and Cross-Section Data
Noriaki Nakao, Shun-ichi Tanaka, Takashi Nakamura, Kazuo Shin, Susumu Tanaka, Hiroshi Takada, Shinichiro Meigo, Yoshihiro Nakane, Yukio Sakamoto, Mamoru Baba
Nuclear Science and Engineering | Volume 124 | Number 2 | October 1996 | Pages 243-257
Technical Paper | doi.org/10.13182/NSE96-A28575
Effects of the Photon Cross Sections and Energy-Absorption Coefficients of Air to the Gamma-Ray Point Isotropic Exposure Buildup Factors
Hideo Hirayama
Nuclear Science and Engineering | Volume 124 | Number 2 | October 1996 | Pages 258-270
Technical Paper | doi.org/10.13182/NSE96-A28576
The ⁵⁹Co( n,xα) Reaction from 5 to 50 MeV
S. M. Grimes, C. E. Brient, F. B. Bateman, M. B. Chadwick, R. C. Haight, T. M. Lee‚ S. M. Sterbenz, P. G. Young F. C. Goeckner, O. A. Wasson, H. Vonach
Nuclear Science and Engineering | Volume 124 | Number 2 | October 1996 | Pages 271-279
Technical Paper | doi.org/10.13182/NSE96-A28577
Analysis of Nuclear Power Transmutation Potential at Equilibrium
M. Salvatores, I. Slessarev, A. Tchistiakov
Nuclear Science and Engineering | Volume 124 | Number 2 | October 1996 | Pages 280-290
Technical Paper | doi.org/10.13182/NSE96-A28578
Optimization of Nonanalog Monte Carlo Games Using Differential Operator Sampling
P. K. Sarkar, Herbert Rief
Nuclear Science and Engineering | Volume 124 | Number 2 | October 1996 | Pages 291-308
Technical Paper | doi.org/10.13182/NSE96-A28579
A Modified P₃-Like Approximation to the Transport Equation
Bingjing Su, G. C. Pomraning
Nuclear Science and Engineering | Volume 124 | Number 2 | October 1996 | Pages 309-319
Technical Paper | doi.org/10.13182/NSE96-A28580
Boundary Condition Perturbations in Transport Theory
Farzad Rahnema
Nuclear Science and Engineering | Volume 124 | Number 2 | October 1996 | Pages 320-326
Technical Paper | doi.org/10.13182/NSE96-A28581
Quantitative Method to Measure Void Fraction of Two-Phase Flow Using Electronic Imaging with Neutrons
K. Mishima, T. Hibiki
Nuclear Science and Engineering | Volume 124 | Number 2 | October 1996 | Pages 327-338
Technical Paper | doi.org/10.13182/NSE96-A28582
Neural Network-Based Fault Detections in a Pressurized Water Reactor Pressurizer
M. Marseguerra, M. E. Ricotti, E. Zio
Nuclear Science and Engineering | Volume 124 | Number 2 | October 1996 | Pages 339-348
Techniacl Paper | doi.org/10.13182/NSE96-A28583
A Semiempirical Method to Calculate Continuum Gamma-Ray Spectra and Multiplicities from Neutron-Induced Reactions
Sheng Fan, Zhixiang Zhao
Nuclear Science and Engineering | Volume 124 | Number 2 | October 1996 | Pages 349-357
Technical Note | doi.org/10.13182/NSE96-A28584
A Note on the P_N Method with Mark Boundary Conditions
R. D. M. Garcia, C.E. Siewert
Nuclear Science and Engineering | Volume 124 | Number 2 | October 1996 | Pages 358-360
Technical Note | doi.org/10.13182/NSE96-2
Autoregressive Moving Average Inverse Dynamics for Rhodium Self-Powered Neutron Detector
Charles W. Mayo, Lian Yan
Nuclear Science and Engineering | Volume 124 | Number 2 | October 1996 | Pages 361-363
Technical Note | doi.org/10.13182/NSE96-A28586

Number 3

Table of Contents

A Hybrid Multigroup/Continuous-Energy Monte Carlo Method for Solving the Boltzmann-Fokker-Planck Equation
J. E. Morel, Leonard J. Lorence, Jr., Ronald P. Kensek, John A. Halbleib, D. P. Sloan
Nuclear Science and Engineering | Volume 124 | Number 3 | November 1996 | Pages 369-389
Technical Paper | doi.org/10.13182/NSE124-369
Higher Order Fokker-Planck Operators
G. C. Pomraning
Nuclear Science and Engineering | Volume 124 | Number 3 | November 1996 | Pages 390-397
Technical Paper | doi.org/10.13182/NSE96-A17918
Forward-Adjoint Monte Carlo Coupling with No Statistical Error Propagation
S. N. Cramer
Nuclear Science and Engineering | Volume 124 | Number 3 | November 1996 | Pages 398-416
Technical Paper | doi.org/10.13182/NSE96-A17919
Wavelet Theory for Solution of the Neutron Diffusion Equation
Nam Zin Cho, Chang Je Park
Nuclear Science and Engineering | Volume 124 | Number 3 | November 1996 | Pages 417-430
Technical Paper | doi.org/10.13182/NSE96-A17920
The Derivation and Proper Use of Stewart’s Formula for Thermal Neutron Self-Shielding in Scattering Media
M. Blaauw
Nuclear Science and Engineering | Volume 124 | Number 3 | November 1996 | Pages 431-435
Technical Paper | doi.org/10.13182/NSE96-A17921
Mass Spectrometric Measurements of Fission Product Effusion from Irradiated Light Water Reactor Fuel
F. Capone, J. P. Hiernaut, M. Martellenghi, C. Ronchi
Nuclear Science and Engineering | Volume 124 | Number 3 | November 1996 | Pages 436-454
Technical Paper | doi.org/10.13182/NSE96-A17922
Systematic Evaluation of Neutron Shielding Effects for Materials
K. Ueki, A. Ohashi, N. Nariyama, S. Nagayama, T. Fujita, K. Hattori, Y. Anayama
Nuclear Science and Engineering | Volume 124 | Number 3 | November 1996 | Pages 455-464
Technical Paper | doi.org/10.13182/NSE124-455
Thermalization of Neutrons in Graphite: Status and Error Analysis
F. C. Difilippo, J. P. Renier, B. A. Worley
Nuclear Science and Engineering | Volume 124 | Number 3 | November 1996 | Pages 465-472
Technical Paper | doi.org/10.13182/NSE96-A17924
Kinetics of Dissolution of Uranium Metal Foil by Alkaline Hydrogen Peroxide
Daojie Dong, George F. Vandegrift
Nuclear Science and Engineering | Volume 124 | Number 3 | November 1996 | Pages 473-481
Technical Paper | doi.org/10.13182/NSE96-A17925
Fission Cross-Section Measurements of the Odd-Odd Isotopes ²³²Pa, ²³⁸Np, and ²³⁶Np
Y. Danon, M. S. Moore, P. E. Koehler, P. E. Littleton, G. G. Miller, M. A. Ott, L. J. Rowton, W. A. Taylor, J. B. Wilhelmy, M. A. Yates, A. D. Carlson, R. Harper, R. Hilko
Nuclear Science and Engineering | Volume 124 | Number 3 | November 1996 | Pages 482-491
Technical Paper | doi.org/10.13182/NSE96-A17926
Statistical Model Calculations of the ²³²U Fission Cross Section
Vladimir M. Maslov, Yasuyuki Kikuchi
Nuclear Science and Engineering | Volume 124 | Number 3 | November 1996 | Pages 492-497
Technical Note | doi.org/10.13182/NSE96-A17927