ANS / Publications / Journals / Nuclear Science and Engineering

Linear Transport in Correlated Stochastic Media

J. Devooght

Nuclear Science and Engineering / Volume 124 / Number 1 / September 1996 / Pages 1-17

Technical Paper / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NSE96-A24235

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NSE96-A28586

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NSE96-A17927