ANS / Publications / Journals / Nuclear Science and Engineering

A Parametric Study of the DUPIC Fuel Cycle to Reflect Pressurized Water Reactor Fuel Management Strategy

Daniel Rozon, Wei Shen

Nuclear Science and Engineering / Volume 138 / Number 1 / May 2001 / Pages 1-25

Technical Paper / dx.doi.org/10.13182/NSE138-1-25

Split-Cell Exponential Characteristic Transport Method for Unstructured Tetrahedral Meshes

Charles R. Brennan, Rodney L. Miller, Kirk A. Mathews

Nuclear Science and Engineering / Volume 138 / Number 1 / May 2001 / Pages 26-44

Technical Paper / dx.doi.org/10.13182/NSE01-A2200

Multidimensional Deterministic Nuclear Data Sensitivity and Uncertainty Code System: Method and Application

Ivan Kodeli

Nuclear Science and Engineering / Volume 138 / Number 1 / May 2001 / Pages 45-66

Technical Paper / dx.doi.org/10.13182/NSE00-43

Boiling Water Reactor Loading Pattern Optimization Using Simple Linear Perturbation and Modified Tabu Search Methods

Suetsugu Jagawa, Takashi Yoshii, Akihiro Fukao

Nuclear Science and Engineering / Volume 138 / Number 1 / May 2001 / Pages 67-77

Technical Paper / dx.doi.org/10.13182/NSE00-44

Transient Criticality in Fissile Solutions—Compressibility Effects

C. C. Pain, C. R. E. de Oliveira, A. J. H. Goddard, A. P. Umpleby

Nuclear Science and Engineering / Volume 138 / Number 1 / May 2001 / Pages 78-95

Technical Paper / dx.doi.org/10.13182/NSE138-78

An Approximate Monte Carlo Adaptive Importance Sampling Method

Thomas E. Booth

Nuclear Science and Engineering / Volume 138 / Number 1 / May 2001 / Pages 96-103

Technical Paper / dx.doi.org/10.13182/NSE01-A2204

High-Resolution Measurements and Calculations of Photon-Production Cross Sections for ¹⁶O(n,x) Reactions Induced by Neutrons with Energies Between 4 and 200 MeV

R. O. Nelson, M. B. Chadwick, A. Michaudon, P. G. Young

Nuclear Science and Engineering / Volume 138 / Number 2 / June 2001 / Pages 105-144

Technical Paper / dx.doi.org/10.13182/NSE01-A2205

Measurement of the Thick-Target ⁹Be(p,n) Neutron Energy Spectra

W. B. Howard, S. M. Grimes, T. N. Massey, S. I. Al-Quraishi, D. K. Jacobs, C. E. Brient, J. C. Yanch

Nuclear Science and Engineering / Volume 138 / Number 2 / June 2001 / Pages 145-160

Technical Paper / dx.doi.org/10.13182/NSE01-A2206

A Generic Model for the Resuspension of Multilayer Aerosol Deposits by Turbulent Flow

H. Friess, G. Yadigaroglu

Nuclear Science and Engineering / Volume 138 / Number 2 / June 2001 / Pages 161-176

Technical Paper / dx.doi.org/10.13182/NSE01-A2207

Eigenvalue Sensitivity Theory for Resonance-Shielded Cross Sections

M. L. Williams, B. L. Broadhead, C. V. Parks

Nuclear Science and Engineering / Volume 138 / Number 2 / June 2001 / Pages 177-191

Technical Paper / dx.doi.org/10.13182/NSE00-56

Unified Formulation of Nodal Expansion Method and Analytic Nodal Method Solutions to Two-Group Diffusion Equations

Hyun Chul Lee, Chang Hyo Kim

Nuclear Science and Engineering / Volume 138 / Number 2 / June 2001 / Pages 192-204

Technical Paper / dx.doi.org/10.13182/NSE01-A2209

Inherent and Passive Safety Sodium-Cooled Fast Reactor Core Design with Minor Actinide and Fission Product Incineration

Hideaki Kuraishi, Tetsuo Sawada, Hisashi Ninokata, Hiroshi Endo

Nuclear Science and Engineering / Volume 138 / Number 3 / July 2001 / Pages 205-232

Technical Paper / dx.doi.org/10.13182/NSE01-A2210

Improved Gamma-Heating Calculational Methods for Fast Reactors and Their Validation for Plutonium-Burning Configurations

Anton Lüthi, Rakesh Chawla, Gérald Rimpault

Nuclear Science and Engineering / Volume 138 / Number 3 / July 2001 / Pages 233-255

Technical Paper / dx.doi.org/10.13182/NSE01-A2211

Discontinuous Finite Element S_N Methods on Three-Dimensional Unstructured Grids

Todd A. Wareing, John M. McGhee, Jim E. Morel, Shawn D. Pautz

Nuclear Science and Engineering / Volume 138 / Number 3 / July 2001 / Pages 256-268

Technical Paper / dx.doi.org/10.13182/NSE138-256

Fast Tree Multigrid Transport Application for the Simplified P₃ Approximation

Petri Kotiluoto

Nuclear Science and Engineering / Volume 138 / Number 3 / July 2001 / Pages 269-278

Technical Paper / dx.doi.org/10.13182/NSE01-A2213

Sensitivity Analysis of Nuclide Importance to One-Group Neutron Cross Sections

Hiroshi Sekimoto, Atsushi Nemoto, Yoshikane Yoshimura

Nuclear Science and Engineering / Volume 138 / Number 3 / July 2001 / Pages 279-294

Technical Paper / dx.doi.org/10.13182/NSE01-A2214

Homogeneous ^242mAm-Fueled Reactor for Neutron Capture Therapy

Y. Ronen, M. Aboudy, D. Regev

Nuclear Science and Engineering / Volume 138 / Number 3 / July 2001 / Pages 295-304

Technical Paper / dx.doi.org/10.13182/NSE01-A2215

Design of a Receding Horizon Control System for Nuclear Reactor Power Distribution

Man Gyun Na

Nuclear Science and Engineering / Volume 138 / Number 3 / July 2001 / Pages 305-314

Technical Paper / dx.doi.org/10.13182/NSE01-A2216

Importance of Delayed Neutrons on the Coupled Neutronic-Thermohydraulic Stability of a Natural Circulation Heavy Water-Moderated Boiling Light Water-Cooled Reactor

A. K. Nayak, M. Aritomi, V. Venkat Raj

Nuclear Science and Engineering / Volume 138 / Number 3 / July 2001 / Pages 315-321

Technical Note / dx.doi.org/10.13182/NSE01-A2217