ANS / Publications / Journals / Nuclear Science and Engineering

Differential Neutron Production Cross Sections for 597-MeV Protons

W. B. Amian, R. C. Byrd, D. A. Clark, C. A. Goulding, M. M. Meier, G. L. Morgan, C. E. Moss

Nuclear Science and Engineering / Volume 115 / Number 1 / September 1993 / Pages 1-12

Technical Paper / dx.doi.org/10.13182/NSE93-A35517

Shielding Measurements for 230-MeV Protons

J. V. Siebers, P. M. DeLuca, Jr., D. W. Pearson, G. Coutrakon

Nuclear Science and Engineering / Volume 115 / Number 1 / September 1993 / Pages 13-23

Technical Paper / dx.doi.org/10.13182/NSE93-A35518

Measurement and Calculations of Angular Neutron Flux Spectra from Iron Slabs Bombarded with 14.8-MeV Neutrons

Yukio Oyama, Kazuaki Kosako, Hiroshi Maekawa

Nuclear Science and Engineering / Volume 115 / Number 1 / September 1993 / Pages 24-37

Technical Paper / dx.doi.org/10.13182/NSE93-A35519

Observed Penetration of 14-MeV Neutrons in Various Materials

C. M. Logan, T. T. Komoto

Nuclear Science and Engineering / Volume 115 / Number 1 / September 1993 / Pages 38-42

Technical Paper / dx.doi.org/10.13182/NSE93-A35520

Continuum Angular Distributions in the Transition Regions

C.Kalbach

Nuclear Science and Engineering / Volume 115 / Number 1 / September 1993 / Pages 43-49

Technical Paper / dx.doi.org/10.13182/NSE93-A35521

Reactivity Feedback Mechanisms in Aqueous Fissile Solutions

Drew E. Kornreich

Nuclear Science and Engineering / Volume 115 / Number 1 / September 1993 / Pages 50-61

Technical Paper / dx.doi.org/10.13182/NSE93-1

One-Dimensional Bimodal Model of Vibration and Impacting of Instrument Tubes in a Boiling Water Reactor

E. Laggiard, J. Runkel, D. Stegemann

Nuclear Science and Engineering / Volume 115 / Number 1 / September 1993 / Pages 62-70

Technical Paper / dx.doi.org/10.13182/NSE93-A35523

Determination of the Excitation Function of the (n,xt) Process on Beryllium via Activation in Diverse Neutron Fields and Unfolding Code Calculations

R. Wölfle, A. Suhaimi, S. M. Qaim

Nuclear Science and Engineering / Volume 115 / Number 1 / September 1993 / Pages 71-75

Technical Notes / dx.doi.org/10.13182/NSE93-A35524

A Measurement of the Effective Delayed Neutron Fraction of the Westinghouse Idaho Nuclear Company Slab Tank Assembly Using Rossi-α Techniques

Gregory D. Spriggs

Nuclear Science and Engineering / Volume 115 / Number 1 / September 1993 / Pages 76-80

Technical Notes / dx.doi.org/10.13182/NSE93-A35525

Use of Padé Approximations in the Analytical Evaluation of the J(θ,β) Function and Its Temperature Derivative

R. S. Keshavamurthy, R. Harish

Nuclear Science and Engineering / Volume 115 / Number 1 / September 1993 / Pages 81-88

Technical Notes / dx.doi.org/10.13182/NSE93-A35526

Scaling of Complex Phenomena in System Thermal Hydraulics

R. Bovalini, F. D’Auria, G. M. Galassi

Nuclear Science and Engineering / Volume 115 / Number 2 / October 1993 / Pages 89-111

Technical Paper / dx.doi.org/10.13182/NSE93-A28521

Consistent B_n Theory for Slab Lattices

R. Roy, A. Hébert, G. Marleau

Nuclear Science and Engineering / Volume 115 / Number 2 / October 1993 / Pages 112-128

Technical Paper / dx.doi.org/10.13182/NSE93-A28522

Development of a Third-Generation Superhomogénéisation Method for the Homogenization of a Pressurized Water Reactor Assembly

A. Hébert, G. Mathonnière

Nuclear Science and Engineering / Volume 115 / Number 2 / October 1993 / Pages 129-141

Technical Paper / dx.doi.org/10.13182/NSE115-129

Application of H_∞Control Theory to Power Control of a Nonlinear Reactor Model

Katsuo Suzuki, Junya Shimazaki, Yoshikuni Shinohara

Nuclear Science and Engineering / Volume 115 / Number 2 / October 1993 / Pages 142-151

Technical Paper / dx.doi.org/10.13182/NSE92-112

Optimal Fuel Loading Pattern Design Using an Artificial Neural Network and a Fuzzy Rule-Based System

Han Gon Kim, Soon Heung Chang, Byung Ho Lee

Nuclear Science and Engineering / Volume 115 / Number 2 / October 1993 / Pages 152-163

Technical Paper / dx.doi.org/10.13182/NSE93-A28525

Normalization and Minimum Values of the ²³⁹Pu Fission Cross Section

L. W. Weston, J. H. Todd, H.Derrien

Nuclear Science and Engineering / Volume 115 / Number 2 / October 1993 / Pages 164-172

Technical Paper / dx.doi.org/10.13182/NSE93-A28526

Normalization of the ²³⁹Pu Fission Cross Section

C. Wagemans, P. Van Uffelen, A. Deruytter, R. Barthélémy, J. Van Gils

Nuclear Science and Engineering / Volume 115 / Number 2 / October 1993 / Pages 173-176

Technical Paper / dx.doi.org/10.13182/NSE93-A28527

A Collision Probability Analysis of the Double-Heterogeneity Problem

A. Hébert

Nuclear Science and Engineering / Volume 115 / Number 2 / October 1993 / Pages 177-184

Technical Note / dx.doi.org/10.13182/NSE115-177

An Experimental Investigation of the Effects of Surfactants on the Severity of Vapor Explosions

M. G. Kowal,M. F. Dowling, S. I. Abdel-Khalik

Nuclear Science and Engineering / Volume 115 / Number 3 / November 1993 / Pages 185-192

Technical Paper / dx.doi.org/10.13182/NSE93-A24048

Influence of Hydrides on Ductile Fracture in the Zr-2.5 Nb Alloy

S. A. Nikulin, M. A. Shtremel, V. G. Khanzhin, B. M. Fateev, V. A. Markelov

Nuclear Science and Engineering / Volume 115 / Number 3 / November 1993 / Pages 193-204

Technical Paper / dx.doi.org/10.13182/NSE93-A24049

Influence of Burnable Gadolinia Poison on Coolant Void Reactivity in a Pressure-Tube-Type Heavy Water Reactor

Yasuki Kowata, Nobuo Fukumura

Nuclear Science and Engineering / Volume 115 / Number 3 / November 1993 / Pages 205-218

Technical Paper / dx.doi.org/10.13182/NSE93-A24050

Numerical Divergence Effects of Equivalence Theory in the Nodal Expansion Method

M. R. Zika, T. J. Downar

Nuclear Science and Engineering / Volume 115 / Number 3 / November 1993 / Pages 219-232

Technical Paper / dx.doi.org/10.13182/NSE93-A24051

Variational Nodal Transport Methods with Anisotropic Scattering

G. Palmiotti, C. B. Carrico, E. E. Lewis

Nuclear Science and Engineering / Volume 115 / Number 3 / November 1993 / Pages 233-243

Technical Paper / dx.doi.org/10.13182/NSE92-110

Subspace Iteration for Nonsymmetric Eigenvalue Problems Applied to the λ-Eigenvalue Problem

Matthias G. Döring, Jens Chr. Kalkkuhl, Wolfram Schröder

Nuclear Science and Engineering / Volume 115 / Number 3 / November 1993 / Pages 244-252

Technical Paper / dx.doi.org/10.13182/NSE93-A24053

A Two-Grid Acceleration Scheme for the Multigroup S_n Equations with Neutron Upscattering

B. T. Adams, J. E. Morel

Nuclear Science and Engineering / Volume 115 / Number 3 / November 1993 / Pages 253-264

Technical Paper / dx.doi.org/10.13182/NSE115-253

Cell-Centered Imposed Diffusion Synthetic Acceleration for Weighted Difference Transport Methods

Y. Y. Azmy

Nuclear Science and Engineering / Volume 115 / Number 3 / November 1993 / Pages 265-272

Technical Note / dx.doi.org/10.13182/NSE93-A24055

The Influence of Burnup-Dependent Fission Spectra on Reactor Pressure Vessel Irradiation

Frej Wasastjerna

Nuclear Science and Engineering / Volume 115 / Number 3 / November 1993 / Pages 273-278

Technical Note / dx.doi.org/10.13182/NSE93-A24056

Spent-Fuel Assay Performance and Monte Carlo Analysis of the Rensselaer Slowing-Down-Time Spectrometer

Naeem M. Abdurrahman, Robert C. Block, Donald R. Harris, Rudolf E. Slovacek, Yong-Doek Lee, Francisco Rodriguez-Vera

Nuclear Science and Engineering / Volume 115 / Number 4 / December 1993 / Pages 279-296

Technical Paper / dx.doi.org/10.13182/NSE92-94

Photoexcitation of ^93mNb in the 5- to 30-MeV Gamma-Energy Range

J. Sáfár, L. Lakosi

Nuclear Science and Engineering / Volume 115 / Number 4 / December 1993 / Pages 297-299

Technical Paper / dx.doi.org/10.13182/NSE93-A24059

Total Interaction Cross Sections of Several Sugars for ¹³³Ba Photons

K. P. Gopinathan Nair, Channe Gowda, J. Shylaja Kumari, S. J. Anasuya, T. K. Umesh, Ramakrishna Gowda

Nuclear Science and Engineering / Volume 115 / Number 4 / December 1993 / Pages 300-303

Technical Paper / dx.doi.org/10.13182/NSE93-A24060

Diffusion-Accelerated Solution of the Two-Dimensional S_n Equations with Bilinear-Discontinuous Differencing

J. E. Morel, J. E. Dendy, Jr., T. A. Wareing

Nuclear Science and Engineering / Volume 115 / Number 4 / December 1993 / Pages 304-319

Technical Paper / dx.doi.org/10.13182/NSE93-A24061

Anisotropic Eigenvalue Spectrum Calculations of the Neutron Transport Operator with Low-Order Spatial Expansion Methods

P. Kohut

Nuclear Science and Engineering / Volume 115 / Number 4 / December 1993 / Pages 320-333

Technical Paper / dx.doi.org/10.13182/NSE93-A24062

Depletion Perturbation Theory Within the Framework of an Advanced Hexagonal Nodal Method

T. J. Downar

Nuclear Science and Engineering / Volume 115 / Number 4 / December 1993 / Pages 334-340

Technical Note / dx.doi.org/10.13182/NSE93-A24063

Analysis of Radially Heterogeneous ZPPR-13A Benchmark for Investigating the Spatial Dependence of the Calculated-to-Experimental Ratio for Control Rod Worths

B. Mahalakshmi, P. Mohanakrishnan

Nuclear Science and Engineering / Volume 115 / Number 4 / December 1993 / Pages 341-347

Technical Note / dx.doi.org/10.13182/NSE93-A24064