ANS / Publications / Journals / Nuclear Science and Engineering

Calculation and Evaluation of Cross Sections and Kerma Factors for Neutrons up to 100 MeV on ¹⁶O and ¹⁴N

M. B. Chadwick, P. G. Young

Nuclear Science and Engineering / Volume 123 / Number 1 / May 1996 / Pages 1-16

Technical Paper / dx.doi.org/10.13182/NSE96-A24209

Calculation and Evaluation of Cross Sections and Kerma Factors for Neutrons up to 100 MeV on Carbon

M. B. Chadwick, L. J. Cox, P. G. Young, A.S. Meigooni

Nuclear Science and Engineering / Volume 123 / Number 1 / May 1996 / Pages 17-37

Technical Paper / dx.doi.org/10.13182/NSE96-A24210

The Even-Parity and Simplified Even-Parity Transport Equations in Two-Dimensional x-y Geometry

Taewan Noh, Warren F. Miller, Jr., Jim E. Morel

Nuclear Science and Engineering / Volume 123 / Number 1 / May 1996 / Pages 38-56

Technical Paper / dx.doi.org/10.13182/NSE96-A24211

A Locally Exact Numerical Scheme with Nonoscillation Properties for Stationary Transport Equations with Absorption and Source Terms

Katsuhiro Sakai

Nuclear Science and Engineering / Volume 123 / Number 1 / May 1996 / Pages 57-67

Technical Paper / dx.doi.org/10.13182/NSE96-A24212

Singular Perturbation Solutions of the Neutron Transport Equation

David C. Losey, John C. Lee, William R. Martin, Thomas C. Adamson, Jr.

Nuclear Science and Engineering / Volume 123 / Number 1 / May 1996 / Pages 68-85

Technical Paper / dx.doi.org/10.13182/NSE96-A24213

The FLEXBURN Neutron Transport Code Developed by the S_n Method with Transmission Probabilities in Arbitrary Square Meshes for Light Water Reactor Fuel Assemblies

Takanori Kameyama, Tetsuo Matsumura, Makoto Sasak

Nuclear Science and Engineering / Volume 123 / Number 1 / May 1996 / Pages 86-95

Technical Paper / dx.doi.org/10.13182/NSE96-A24214

Continuous Energy Monte Carlo Calculations of Randomly Distributed Spherical Fuels in High-Temperature Gas-Cooled Reactors Based on a Statistical Geometry Model

Isao Murata, Takamasa Mori, Masayuki Nakagawa

Nuclear Science and Engineering / Volume 123 / Number 1 / May 1996 / Pages 96-109

Technical Paper / dx.doi.org/10.13182/NSE96-A24215

The Two-Region Milne Problem

B.D. Ganapol, G. C. Pomraning

Nuclear Science and Engineering / Volume 123 / Number 1 / May 1996 / Pages 110-120

Technical Paper / dx.doi.org/10.13182/NSE96-A24216

The Effective Fuel Temperature to be Used for Calculating Resonance Absorption in a ²³⁸UO₂ Lump with a Nonuniform Temperature Profile

W. J. M. de Kruijf, A. J. Janssen

Nuclear Science and Engineering / Volume 123 / Number 1 / May 1996 / Pages 121-135

Technical Paper / dx.doi.org/10.13182/NSE94-108

The Effect of Gas Injection Configuration on Two-Phase Countercurrent Flow Limitation in Short Vertical Channels

S. M. Ghiaasiaan, J. D. Bohner, S. I. Abdel-Khalik

Nuclear Science and Engineering / Volume 123 / Number 1 / May 1996 / Pages 136-146

Technical Paper / dx.doi.org/10.13182/NSE96-A24218

An Upwind Numerical Method for Two-Fluid Two-Phase Flow Models

I. Toumi

Nuclear Science and Engineering / Volume 123 / Number 2 / June 1996 / Pages 147-168

Technical Paper / dx.doi.org/10.13182/NSE96-A24180

Numerical Simulations of Nonstationary Fronts and Interfaces by the Godunov Method in Moving Grids

V. E. Fortov, B. Goel, C.-D. Munz, A. L. Ni, A. V. Shutov, O. Yu. Vorobiev

Nuclear Science and Engineering / Volume 123 / Number 2 / June 1996 / Pages 169-189

Technical Paper / dx.doi.org/10.13182/NSE96-A24181

Evaluation of Inherent Distortions in the IIST Facility Using the RELAP5/MOD3 Code

Yuh-Ming Ferng

Nuclear Science and Engineering / Volume 123 / Number 2 / June 1996 / Pages 190-205

Technical Paper / dx.doi.org/10.13182/NSE96-A24182

A Second-Derivative-Based Adaptive Time-Step Method for Spatial Kinetics Calculations

Nicolas Crouzet, Paul J. Turinsky

Nuclear Science and Engineering / Volume 123 / Number 2 / June 1996 / Pages 206-214

Technical Paper / dx.doi.org/10.13182/NSE96-A24183

Improvement of Gamma-Ray S_n Transport Calculations Including Coherent and Incoherent Scatterings and Secondary Sources of Bremsstrahlung and Fluorescence: Determination of Gamma-Ray Buildup Factors

P. Ridoux, S. Kitsos, C. M. Diop, A. Assad, J. C. Nimal

Nuclear Science and Engineering / Volume 123 / Number 2 / June 1996 / Pages 215-227

Technical Paper / dx.doi.org/10.13182/NSE96-A24184

Inconsistencies in Widely Used Monte Carlo Methods for Precise Calculation of Radial Resonance Captures in Uranium Fuel Rods

Donald Bogart

Nuclear Science and Engineering / Volume 123 / Number 2 / June 1996 / Pages 228-237

Technical Paper / dx.doi.org/10.13182/NSE96-A24185

The Accident Sequence Precursor Analysis: Review of the Methods and New Insights

M. Modarres, H. Martz, M. Kaminskiy

Nuclear Science and Engineering / Volume 123 / Number 2 / June 1996 / Pages 238-258

Technical Paper / dx.doi.org/10.13182/NSE96-A24186

A Method for Measurement of Delayed Neutron Parameters for Liquid-Metal-Cooled Power Reactors

Richard B. Vilim, Richard W. Brock

Nuclear Science and Engineering / Volume 123 / Number 2 / June 1996 / Pages 259-271

Technical Paper / dx.doi.org/10.13182/NSE96-A24187

Benchmark Test of 14-MeV Neutron-Induced Gamma-Ray Production Data in JENDL-3.2 and FENDL/E-1.0 Through Analysis of the OKTAVIAN Experiments

F. Maekawa, Y. Oyama

Nuclear Science and Engineering / Volume 123 / Number 2 / June 1996 / Pages 272-281

Technical Paper / dx.doi.org/10.13182/NSE96-A24188

Skyshine Line-Beam Response Functions for 20- to 100-MeV Photons

R. C. Brockhoff, J. Kenneth Shultis, Richard E. Faw

Nuclear Science and Engineering / Volume 123 / Number 2 / June 1996 / Pages 282-288

Technical Paper / dx.doi.org/10.13182/NSE96-A24189

Effect of an Overhead Shield on Gamma-Ray Skyshine

Mark H. Stedry, J. Kenneth Shultis, Richard E. Faw

Nuclear Science and Engineering / Volume 123 / Number 2 / June 1996 / Pages 289-294

Technical Paper / dx.doi.org/10.13182/NSE96-A24190

Modeling Water Chemistry, Electrochemical Corrosion Potential, and Crack Growth Rate in the Boiling Water Reactor Heat Transport Circuits—II: Simulation of Operating Reactors

Tsung-Kuang Yeh, Digby D. Macdonald

Nuclear Science and Engineering / Volume 123 / Number 2 / June 1996 / Pages 295-304

Technical Paper / dx.doi.org/10.13182/NSE96-A24191

Modeling Water Chemistry, Electrochemical Corrosion Potential, and Crack Growth Rate in the Boiling Water Reactor Heat Transport Circuits —III: Effect of Reactor Power Level

Tsung-Kuang Yeh, Digby D. Macdonald

Nuclear Science and Engineering / Volume 123 / Number 2 / June 1996 / Pages 305-316

Technical Paper / dx.doi.org/10.13182/NSE96-A24192

A Three-Dimensional Time-Dependent Unstructured Tetrahedral-Mesh SP_N Method

J. E. Morel,J. M. McGhee,Edward W. Larsen

Nuclear Science and Engineering / Volume 123 / Number 3 / July 1996 / Pages 319-327

Technical Paper / dx.doi.org/10.13182/NSE96-A24196

Asymptotic Derivation of the Multigroup P₁ and Simplified P_N Equations with Anisotropic Scattering

Edward W. Larsen, J. E. Morel, John M. McGhee

Nuclear Science and Engineering / Volume 123 / Number 3 / July 1996 / Pages 328-342

Technical Paper / dx.doi.org/10.13182/NSE123-328

Asymptotic Derivation of the Fermi Pencil-Beam Approximation

Christoph Börgers,Edward W. Larsen

Nuclear Science and Engineering / Volume 123 / Number 3 / July 1996 / Pages 343-357

Technical Paper / dx.doi.org/10.13182/NSE96-A24198

Application of the B_nTheory to Unit Cell Calculations

R. Roy

Nuclear Science and Engineering / Volume 123 / Number 3 / July 1996 / Pages 358-368

Technical Paper / dx.doi.org/10.13182/NSE96-A24199

Variational Nodal Transport Perturbation Theory

Kirsten F. Laurin-Kovitz,E. E. Lewis

Nuclear Science and Engineering / Volume 123 / Number 3 / July 1996 / Pages 369-380

Technical Paper / dx.doi.org/10.13182/NSE96-A24200

Solution of Mathematical Adjoint Equation for a Higher Order Nodal Expansion Method

Taek Kyum Kim, Chang Hyo Kim

Nuclear Science and Engineering / Volume 123 / Number 3 / July 1996 / Pages 381-391

Technical Paper / dx.doi.org/10.13182/NSE96-A24201

Collision Probability Calculation and Multigroup Flux Solvers Using PVM

A. Qaddouri, R. Roy, M. Mayrand, B. Goulard

Nuclear Science and Engineering / Volume 123 / Number 3 / July 1996 / Pages 392-402

Technical Paper / dx.doi.org/10.13182/NSE96-A24202

An Incomplete Domain Decomposition Preconditioning Method for Nonlinear Nodal Kinetics Calculations

Han Gyu Joo,Thomas J. Downar

Nuclear Science and Engineering / Volume 123 / Number 3 / July 1996 / Pages 403-414

Technical Paper / dx.doi.org/10.13182/NSE96-A24203

A Domain Decomposition Method for Nonlinear Steady-State Flow Computations

Sébastien Clerc

Nuclear Science and Engineering / Volume 123 / Number 3 / July 1996 / Pages 415-420

Technical Paper / dx.doi.org/10.13182/NSE96-A24204

Moving-Particle Semi-Implicit Method for Fragmentation of Incompressible Fluid

S. Koshizuka, Y. Oka

Nuclear Science and Engineering / Volume 123 / Number 3 / July 1996 / Pages 421-434

Technical Paper / dx.doi.org/10.13182/NSE96-A24205

Kalman Filter Application for Distributed Parameter Estimation in Reactor Systems

Robert P. Martin, Robert M. Edwards

Nuclear Science and Engineering / Volume 123 / Number 3 / July 1996 / Pages 435-442

Technical Paper / dx.doi.org/10.13182/NSE96-A24206

Flow Modeling in Heterogeneous Media in the Context of Geologic Nuclear Waste Repositories

Budhi Sagar

Nuclear Science and Engineering / Volume 123 / Number 3 / July 1996 / Pages 443-454

Technical Paper / dx.doi.org/10.13182/NSE96-A24207