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Volume 101

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Number 1

Table of Contents
Comparison of the Response to Small Perturbations in Metal- and Oxide-Fueled Liquid-Metal-Cooled Reactors(Suresh M. Lee)
Response to “Comparison of the Response to Small Perturbations in Metal- and Oxide-Fueled Liquid-Metal-Cooled Reactors” (K. O. Ott)

Interaction of Neutrons with ⁹Be at 14.6 MeV — The Four-Body Breakup 2n + 2α

D. Ferenc, B. Antolković, G. Paić, M. Zadro, S. Blagus

Nuclear Science and Engineering / Volume 101 / Number 1 / January 1989 / Pages 1-7

Technical Paper / dx.doi.org/10.13182/NSE89-A23590

Determination of the Field of View of a Boiling Water Reactor In-Core Detector

Alireza Haghighat, George Kosály

Nuclear Science and Engineering / Volume 101 / Number 1 / January 1989 / Pages 8-25

Technical Paper / dx.doi.org/10.13182/NSE89-A23591

Vapor Pressure Measurements on Liquid Uranium Oxide and (U,Pu) Mixed Oxide

W. Breitung, K. O. Reil

Nuclear Science and Engineering / Volume 101 / Number 1 / January 1989 / Pages 26-40

Technical Paper / dx.doi.org/10.13182/NSE89-A23592

On the Reactivity Effects of Nuclear Fuel Fragmentation with Reference to the Chernobyl Accident

Markku Rajamäki, Frej Wasastjerna

Nuclear Science and Engineering / Volume 101 / Number 1 / January 1989 / Pages 41-47

Technical Paper / dx.doi.org/10.13182/NSE89-A23593

One-Dimensional Transient Fluid Model for Fuel/Coolant Interaction Analysis

C.C. Chu, M. L. Corradini

Nuclear Science and Engineering / Volume 101 / Number 1 / January 1989 / Pages 48-71

Technical Paper / dx.doi.org/10.13182/NSE89-A23594

A Hybrid Collocation-Galerkin-S_n Method for Solving the Boltzmann Transport Equation

J. E. Morel

Nuclear Science and Engineering / Volume 101 / Number 1 / January 1989 / Pages 72-87

Technical Paper / dx.doi.org/10.13182/NSE89-4

Evaluation of Correlated Data Using Partitioned Least Squares: A Minimum-Variance Derivation

D. W. Muir

Nuclear Science and Engineering / Volume 101 / Number 1 / January 1989 / Pages 88-93

Technical Note / dx.doi.org/10.13182/NSE89-A23596

Number 2

Table of Contents

A New Evaluation of the Urania Equation of State Based on Recent Vapor Pressure Measurements

E. A. Fischer

Nuclear Science and Engineering / Volume 101 / Number 2 / February 1989 / Pages 97-116

Technical Paper / dx.doi.org/10.13182/NSE89-A23600

Analytic Predictions of Boiling Film Stability for Conditions Consistent with Light Water Reactor Degraded Core Conditions

Man-Shik Song, Paul J. Turinsky

Nuclear Science and Engineering / Volume 101 / Number 2 / February 1989 / Pages 117-132

Technical Paper / dx.doi.org/10.13182/NSE89-A23601

An Error Estimation for the Implicit Euler Method Recommended for Use in the RELAP4 Family of Codes

Stefan Goos

Nuclear Science and Engineering / Volume 101 / Number 2 / February 1989 / Pages 133-136

Technical Paper / dx.doi.org/10.13182/NSE89-A23602

Benchmark Physics Tests in the Metallic-Fueled Assembly ZPPR-15

H. F. McFarlane, S. B. Brumbach, S. G. Carpenter, P. J. Collins

Nuclear Science and Engineering / Volume 101 / Number 2 / February 1989 / Pages 137-152

Technical Paper / dx.doi.org/10.13182/NSE101-137

A Semianalytical Method to Solve the Linear Fokker-Planck Equation Characterizing Charged-Particle Transport in Spherical Plasmas

S. D. Paranjape, D. C. Sahni

Nuclear Science and Engineering / Volume 101 / Number 2 / February 1989 / Pages 153-165

Technical Paper / dx.doi.org/10.13182/NSE89-A23604

Fine-Mesh Limit of One-Dimensional Nodal Transport Equations

Ely M. Gelbard, Yen-Wan H. Liu, Laura Olvey

Nuclear Science and Engineering / Volume 101 / Number 2 / February 1989 / Pages 166-178

Technical Paper / dx.doi.org/10.13182/NSE89-A23605

Evaluation of Neutron Streaming in Fast Breeder Reactor Fuel Subassembly by Double Heterogeneous Modeling

Toshikazu Takeda, Hironobu Unesaki, Toshihisa Yamamoto, Katsuya Kinjo, Toshio Sanda

Nuclear Science and Engineering / Volume 101 / Number 2 / February 1989 / Pages 179-184

Technical Paper / dx.doi.org/10.13182/NSE89-A23606

Transport Analysis of Measured Neutron Energy Spectra in a Graphite Stack with a Collimated Deuterium-Tritium Neutron Beam

R. Ofek, A. Tsechanski, A. Goldfeld, G. Shani

Nuclear Science and Engineering / Volume 101 / Number 2 / February 1989 / Pages 185-203

Technical Paper / dx.doi.org/10.13182/NSE89-A23607

Number 3

Table of Contents

Vectorized and Multitasked Solution of the Few-Group Neutron Diffusion Equations

Sung-Kyun Zee, Paul J. Turinsky, Zeev Shayer

Nuclear Science and Engineering / Volume 101 / Number 3 / March 1989 / Pages 205-216

Technical Paper / dx.doi.org/10.13182/NSE89-A23609

A Transport Method for Treating Three-Dimensional Lattices of Heterogeneous Cells

R. Roy, A. Hébert, G. Marleau

Nuclear Science and Engineering / Volume 101 / Number 3 / March 1989 / Pages 217-225

Technical Paper / dx.doi.org/10.13182/NSE101-217

Analysis of Spectral Shift Effect on Reactor Dynamics and Its Application to RBMK-1000 and Light Water Reactors

Yoshiro Asahi, Tadashi Watanabe

Nuclear Science and Engineering / Volume 101 / Number 3 / March 1989 / Pages 226-242

Technical Paper / dx.doi.org/10.13182/NSE89-A23611

A Study of the Multiplicity of Power Distributions in a Nuclear Reactor Subject to Reactivity Feedbacks

Chae Y. Yang, Nam Z. Cho

Nuclear Science and Engineering / Volume 101 / Number 3 / March 1989 / Pages 243-258

Technical Paper / dx.doi.org/10.13182/NSE89-A23612

Modeling of an Aerosol in Coupled Chambers

D. R. Simpson, M. M. R. Williams, S. Simons

Nuclear Science and Engineering / Volume 101 / Number 3 / March 1989 / Pages 259-268

Technical Paper / dx.doi.org/10.13182/NSE89-A23613

Role of Spatial Inhomogeneities in Source Term Aerosol Dynamics

J. W. Park, S. K. Loyalka

Nuclear Science and Engineering / Volume 101 / Number 3 / March 1989 / Pages 269-279

Technical Paper / dx.doi.org/10.13182/NSE101-269

Fission-Fragment Energy Deposition in Argon

J. R. Torczynski, R. J. Gross, G. N. Hays, G. A. Harms, D. R. Neal, D. A. McArthur, W. J. Alford

Nuclear Science and Engineering / Volume 101 / Number 3 / March 1989 / Pages 280-284

Technical Paper / dx.doi.org/10.13182/NSE89-A23615

Uncertainties of the ENDF/B-V ²³⁸U Unresolved Resonance Parameters in the Range 4 keV < E < 45.18 keV (MAT=1398, MF=2, MT=251)

G. de Saussure, J. H. Marable

Nuclear Science and Engineering / Volume 101 / Number 3 / March 1989 / Pages 285-292

Technical Paper / dx.doi.org/10.13182/NSE89-A23616

Measurement of the Thermal Neutron Induced Fission Cross Section of ²⁴³Am

C. Wagemans, P. Schillebeeckx, J. P. Bocquet

Nuclear Science and Engineering / Volume 101 / Number 3 / March 1989 / Pages 293-297

Technical Paper / dx.doi.org/10.13182/NSE89-A23617

New JEF/EFF Based MATXS-Formatted Nuclear Data Libraries

P. Vontobel, S. Pelloni

Nuclear Science and Engineering / Volume 101 / Number 3 / March 1989 / Pages 298-301

Technical Note / dx.doi.org/10.13182/NSE89-A23618

Number 4

Table of Contents

Numerical Integration of Hydraulic Network Conservation Equations on MIMD Parallel Computers

Prem N. Mahana, F. N. Trofimenkoff

Nuclear Science and Engineering / Volume 101 / Number 4 / April 1989 / Pages 303-314

Technical Paper / dx.doi.org/10.13182/NSE89-A23620

Mixed Convection in Parallel Channels with Application to the Liquid-Metal Reactor Concept

Victor Iannello, Neil E. Todreas

Nuclear Science and Engineering / Volume 101 / Number 4 / April 1989 / Pages 315-329

Technical Paper / dx.doi.org/10.13182/NSE89-A23621

The Transport Equation in General Geometry

G. C. Pomraning

Nuclear Science and Engineering / Volume 101 / Number 4 / April 1989 / Pages 330-340

Technical Paper / dx.doi.org/10.13182/NSE89-A23622

An S₂ Synthetic Acceleration Scheme for the One-Dimensional S_n Equations with Linear Discontinuous Spatial Differencing

Leonard J. Lorence, Jr., J. E. Morel, Edward W. Larsen

Nuclear Science and Engineering / Volume 101 / Number 4 / April 1989 / Pages 341-351

Technical Paper / dx.doi.org/10.13182/NSE89-A23623

Impact of Coherent Scattering on the Spectra and Energy Deposition of Gamma Rays in Bulk Media

K. V. Subbaiah, A. Natarajan, D. V. Gopinath

Nuclear Science and Engineering / Volume 101 / Number 4 / April 1989 / Pages 352-370

Technical Paper / dx.doi.org/10.13182/NSE89-A23624

Techniques to Quantify the Sensitivity of Deterministic Model Uncertainties

T. Ishigami, E. Cazzoli, M. Khatib-Rahbar, ⁺, S. D. Unwin†

Nuclear Science and Engineering / Volume 101 / Number 4 / April 1989 / Pages 371-383

Technical Paper / dx.doi.org/10.13182/NSE89-A23625

Calculation of the Thermal Disadvantage Factor in a Heterogeneous Slab Cell

A. M. Abdallah

Nuclear Science and Engineering / Volume 101 / Number 4 / April 1989 / Pages 384-388

Technical Note / dx.doi.org/10.13182/NSE89-A23626