ANS / Publications / Journals / Nuclear Science and Engineering

Multidimensional Electron-Photon Transport with Standard Discrete Ordinates Codes

C. R. Drumm

Nuclear Science and Engineering / Volume 127 / Number 1 / September 1997 / Pages 1-21

Technical Paper / dx.doi.org/10.13182/NSE97-A1918

Automatic Variance Reduction for Three-Dimensional Monte Carlo Simulations by the Local Importance Function Transform—I: Analysis

Scott A. Turner, Edward W. Larsen

Nuclear Science and Engineering / Volume 127 / Number 1 / September 1997 / Pages 22-35

Technical Paper / dx.doi.org/10.13182/NSE127-22

Automatic Variance Reduction for Three-Dimensional Monte Carlo Simulations by the Local Importance Function Transform—II: Numerical Results

Scott A. Turner, Edward W. Larsen

Nuclear Science and Engineering / Volume 127 / Number 1 / September 1997 / Pages 36-53

Technical Paper / dx.doi.org/10.13182/NSE127-36

Confidence Interval Procedures for Monte Carlo Transport Simulations

S. P. Pederson, R. A. Forster, T. E. Booth

Nuclear Science and Engineering / Volume 127 / Number 1 / September 1997 / Pages 54-77

Technical Paper / dx.doi.org/10.13182/NSE97-A1921

Difficulties in Vector-Parallel Processing of Monte Carlo Codes

Kenji Higuchi, Kiyoshi Asai, Yukihiro Hasegawa

Nuclear Science and Engineering / Volume 127 / Number 1 / September 1997 / Pages 78-88

Technical Paper / dx.doi.org/10.13182/NSE97-A1922

Effect of a 0.3-eV Resonance Cross Section for Plutonium on the Coolant Void Reactivity in a Heavy Water Lattice

Yasuki Kowata, Nobuo Fukumura

Nuclear Science and Engineering / Volume 127 / Number 1 / September 1997 / Pages 89-103

Technical Paper / dx.doi.org/10.13182/NSE97-A1923

R-Matrix Analysis of the ²⁴⁰Pu Neutron Cross Sections in the Thermal to 5700-eV Energy Range

O. Bouland, H. Derrien, N. M. Larson, L. C. Leal

Nuclear Science and Engineering / Volume 127 / Number 2 / October 1997 / Pages 105-129

Technical Paper / dx.doi.org/10.13182/NSE127-105

Partial-Wave Analysis with the Optical Model for the Resolved and Unresolved Resonance Regions of ⁵⁶Fe

Toshihiko Kawano, Fritz H. Fröhner

Nuclear Science and Engineering / Volume 127 / Number 2 / October 1997 / Pages 130-138

Technical Paper / dx.doi.org/10.13182/NSE97-A28592

A Composite Nodal Finite Element for Hexagons

J. P. Hennart, E. H. Mund, E. Del Valle

Nuclear Science and Engineering / Volume 127 / Number 2 / October 1997 / Pages 139-153

Technical Paper / dx.doi.org/10.13182/NSE97-A28593

Variational Nodal Transport Methods with Heterogeneous Nodes

T. H. Fanning, G. Palmiotti

Nuclear Science and Engineering / Volume 127 / Number 2 / October 1997 / Pages 154-168

Technical Paper / dx.doi.org/10.13182/NSE97-A28594

Discrete Ordinates Methods in xy Geometry with Spatially Varying Angular Discretization

Guillaume Bal, Xavier Warin

Nuclear Science and Engineering / Volume 127 / Number 2 / October 1997 / Pages 169-181

Technical Paper / dx.doi.org/10.13182/NSE97-A28595

A Non-Gaussian Treatment of Radiation Pencil Beams

G. C. Pomraning

Nuclear Science and Engineering / Volume 127 / Number 2 / October 1997 / Pages 182-198

Technical Paper / dx.doi.org/10.13182/NSE97-A28596

Parameter Estimation Toward Fault Diagnosis in Nonlinear Systems Using a Markov Model of System Dynamics

Laurian Dinca, Tunc Aldemir

Nuclear Science and Engineering / Volume 127 / Number 2 / October 1997 / Pages 199-219

Technical Paper / dx.doi.org/10.13182/NSE97-A28597

Heat Transfer Characteristics of Reflux Condensation Phenomena in a Single Vertical Tube

Gung-Huei Chou, Jyh-Chen Chen

Nuclear Science and Engineering / Volume 127 / Number 2 / October 1997 / Pages 220-229

Technical Paper / dx.doi.org/10.13182/NSE97-A28598

Neutron Skyshine Calculations with the Integral Line-Beam Method

Ah Auu Gui, J. Kenneth Shultis, Richard E. Faw

Nuclear Science and Engineering / Volume 127 / Number 2 / October 1997 / Pages 230-237

Technical Note / dx.doi.org/10.13182/NSE97-A28599

Multiple Recycling of Light Water Reactor Waste Plutonium in a Fast Spectrum Core

M. Segev, A. Misulovin, A. Galperin

Nuclear Science and Engineering / Volume 127 / Number 2 / October 1997 / Pages 238-244

Technical Note / dx.doi.org/10.13182/NSE97-A28600

Experimental and Calculated Scandium Threshold Reaction Cross Sections Averaged over a ²³⁵U Fission Neutron Spectrum

P. M. Suárez, M. A. Arribére, S. Ribeiro Guevara, A. J. Kestelman

Nuclear Science and Engineering / Volume 127 / Number 3 / November 1997 / Pages 245-261

Technical Paper / dx.doi.org/10.13182/NSE97-A1934

Neutronic Analysis of Critical Configurations in Geologic Repositories: I - Weapons-Grade Plutonium

Ehud Greenspan, J. Vujic, J. Burch

Nuclear Science and Engineering / Volume 127 / Number 3 / November 1997 / Pages 262-291

Technical Paper / dx.doi.org/10.13182/NSE97-A1935

Hydrolysis of Zinc Ion and Solubility of Zinc Oxide in High-Temperature Aqueous Systems

Yukiko Hanzawa, Daisuke Hiroishi, Chihiro Matsuura, Kenkichi Ishigure, Masashi Nagao, Masashi Haginuma

Nuclear Science and Engineering / Volume 127 / Number 3 / November 1997 / Pages 292-299

Technical Paper / dx.doi.org/10.13182/NSE97-03

Development of a Generalized Critical Heat Flux Correlation Through the Alternating Conditional Expectation Algorithm

Han Gon Kim, John C. Lee

Nuclear Science and Engineering / Volume 127 / Number 3 / November 1997 / Pages 300-316

Technical Paper / dx.doi.org/10.13182/NSE97-A1937

Numerical Evaluation of the Three-Dimensional Searchlight Problem in a Half-Space

D. E. Kornreich, B. D. Ganapol

Nuclear Science and Engineering / Volume 127 / Number 3 / November 1997 / Pages 317-337

Technical Paper / dx.doi.org/10.13182/NSE97-A1938

Exponential Convergence on a Continuous Monte Carlo Transport Problem

Thomas E. Booth

Nuclear Science and Engineering / Volume 127 / Number 3 / November 1997 / Pages 338-345

Technical Paper / dx.doi.org/10.13182/NSE97-A1939

Mixed Integer Programming for Pressurized Water Reactor Fuel-Loading-Pattern Optimization

Taek Kyum Kim, Chang Hyo Kim

Nuclear Science and Engineering / Volume 127 / Number 3 / November 1997 / Pages 346-357

Technical Paper / dx.doi.org/10.13182/NSE97-A1940