Volume 73

Number 1

Table of Contents
The Influence of Boundary Conditions on the Precision of the Eigenvalues of the Boltzmann Equation(C. Syros, P. Theocharopoulos)
Reply to “The Influence of Boundary Conditions on the Precision of the Eigenvalues of the Boltzmann Equation”(E. B. Dahl, N. G. Sjöstrand)
Comments on “Neutron-Induced Fission in a DT-Plutonium Plasma”(F. Winterberg)
Reply to “Comments on ‘Neutron-Induced Fission in a DT-Plutonium Plasma’”
Radiation Shielding and Dosimetry(Karl Z. Morgan)
Corrigendum

Markovian Reliability Analysis Under Uncertainty with an Application on the Shutdown System of the Clinch River Breeder Reactor

Ioannis A. Papazoglou, Elias P. Gyftopoulos

Nuclear Science and Engineering / Volume 73 / Number 1 / January 1980 / Pages 1-18

Technical Paper / dx.doi.org/10.13182/NSE80-A18703

Heat Transfer and Pressure Drop in Sodium Boiling in Tubes

Yu. A. Zeigarnick, V. D. Litvinov

Nuclear Science and Engineering / Volume 73 / Number 1 / January 1980 / Pages 19-28

Technical Paper / dx.doi.org/10.13182/NSE80-A18704

Radiation Damage by High-Energy Neutrons

William Primak

Nuclear Science and Engineering / Volume 73 / Number 1 / January 1980 / Pages 29-34

Technical Paper / dx.doi.org/10.13182/NSE80-A18705

Neutron Spectra from Monoenergetic Source Neutrons After Multiple Reflection Between Plane-Parallel Concrete Interfaces

William K. Hagan, G. L. Simmons

Nuclear Science and Engineering / Volume 73 / Number 1 / January 1980 / Pages 35-41

Technical Paper / dx.doi.org/10.13182/NSE80-A18706

Fission Product Yields for Thermal-Neutron Fission of Plutonium-239

J. K. Dickens, J. W. McConnell

Nuclear Science and Engineering / Volume 73 / Number 1 / January 1980 / Pages 42-55

Technical Paper / dx.doi.org/10.13182/NSE80-A18707

Some Results of Transfer Matrix Calculations for Thermal Neutrons

Seong-Youn Kim, Raphael Aronson

Nuclear Science and Engineering / Volume 73 / Number 1 / January 1980 / Pages 56-65

Technical Paper / dx.doi.org/10.13182/NSE80-A18708

Variance Versus Efficiency in Transport Monte Carlo

Iván Lux

Nuclear Science and Engineering / Volume 73 / Number 1 / January 1980 / Pages 66-75

Technical Paper / dx.doi.org/10.13182/NSE80-A18709

Convergence Rates of Spatial Difference Equations for the Discrete-Ordinates Neutron Transport Equations in Slab Geometry

Edward W. Larsen, Warren F. Miller, Jr.

Nuclear Science and Engineering / Volume 73 / Number 1 / January 1980 / Pages 76-83

Technical Paper / dx.doi.org/10.13182/NSE80-3

Probability Level of Readiness in Supervised Protective Systems for Nuclear Reactors

J. M. Kontoleon

Nuclear Science and Engineering / Volume 73 / Number 1 / January 1980 / Pages 84-86

Technical Note / dx.doi.org/10.13182/NSE80-A18711

Comparison of One- and Two-Dimensional Cross-Section Sensitivity Calculations for a Fusion Reactor Shielding Experiment

Y. Seki, R. T. Santoro, E. M. Oblow, J. L. Lucius

Nuclear Science and Engineering / Volume 73 / Number 1 / January 1980 / Pages 87-93

Technical Note / dx.doi.org/10.13182/NSE80-A18712

Optimized Smoothing in Neutron Spectrum Unfolding by the FERDOR Method

R. H. Johnson, B. W. Wehring, J. J. Dorning

Nuclear Science and Engineering / Volume 73 / Number 1 / January 1980 / Pages 93-97

Technical Note / dx.doi.org/10.13182/NSE80-A18713

Photon Point Source Buildup Factors for Air, Water, and Iron

A. B. Chilton, C. M. Eisenhauer, G. L. Simmons

Nuclear Science and Engineering / Volume 73 / Number 1 / January 1980 / Pages 97-107

Technical Note / dx.doi.org/10.13182/NSE80-A18714

Number 2

Table of Contents
The Particle Spectrum from a D-T Plasma(M. M. R. Williams)

Monte Carlo Treatment for Neutral Particle Transport Problems in a Toroidal Plasma

S. Inoue, Y. Taji, Y. Nakahara, T. Suzuki

Nuclear Science and Engineering / Volume 73 / Number 2 / February 1980 / Pages 119-124

Technical Paper / dx.doi.org/10.13182/NSE80-A18692

A Rigorous Treatment of Transverse Buckling Effects in Two-Dimensional Neutron Transport Computations

R. N. Blomquist, E. E. Lewis

Nuclear Science and Engineering / Volume 73 / Number 2 / February 1980 / Pages 125-139

Technical Paper / dx.doi.org/10.13182/NSE80-A18693

Time-Optimal Control of Spatial Xenon Oscillations to a Generalized Target

Earl J. Schulz, John C. Lee

Nuclear Science and Engineering / Volume 73 / Number 2 / February 1980 / Pages 140-152

Technical Paper / dx.doi.org/10.13182/NSE80-A18694

Experimental Determination of Photofission Neutron Multiplicities for ²³⁵U, ²³⁶U, ²³⁸U, and ²³²Th Using Monoenergetic Photons

J. T. Caldwell, E. J. Dowdy, R. A. Alvarez, B. L. Berman, P. Meyer

Nuclear Science and Engineering / Volume 73 / Number 2 / February 1980 / Pages 153-163

Technical Paper / dx.doi.org/10.13182/NSE80-A18695

Resonance Absorption in High-Temperature Gas-Cooled Reactor Fuel with Double Heterogeneity

Keiichiro Tsuchihashi, Yukio Ishiguro, Kunio Kaneko

Nuclear Science and Engineering / Volume 73 / Number 2 / February 1980 / Pages 164-173

Technical Paper / dx.doi.org/10.13182/NSE80-A18696

^{100,101,102,104,}Ru(n, γ) and ¹⁰³Rh(n, γ) Cross Sections Above 2.6 keV

R. L. Macklin, J. Halperin

Nuclear Science and Engineering / Volume 73 / Number 2 / February 1980 / Pages 174-185

Technical Paper / dx.doi.org/10.13182/NSE80-A18697

Scattering of MeV Neutrons from Elemental Iron

A. Smith, P. Guenther

Nuclear Science and Engineering / Volume 73 / Number 2 / February 1980 / Pages 186-195

Technical Paper / dx.doi.org/10.13182/NSE80-A18698

Numerical Simulation of Boiling Water Reactor Vent-Clearing Hydrodynamics

B. D. Nichols, C. W. Hirt

Nuclear Science and Engineering / Volume 73 / Number 2 / February 1980 / Pages 196-209

Technical Paper / dx.doi.org/10.13182/NSE80-A18699

Time-Dependent Generalized Perturbation Theory for Coupled Neutron-Nuclide Problems

E. Greenspan, M. L. Williams, J. H. Marable

Nuclear Science and Engineering / Volume 73 / Number 2 / February 1980 / Pages 210-218

Technical Note / dx.doi.org/10.13182/NSE80-A18700

Number 3

Table of Contents
Concrete Buildup Factors Based on the American National Standard for Flux-to-Dose-Rate Conversion(A. B. Chilton, R. W. Brown)
Comment on “Concrete Buildup Factors Based on the American National Standard for Flux-to-Dose-Rate Conversion”(D. K. Trubey)
Polynomial Expression for the Neutron Escape Probability from an Absorbing Body(Hem Prabha Raghav)
Reply to “Polynomial Expression for the Neutron Escape Probability from an Absorbing Body”(Yung-An Chao)
Comments on the Lyczkowski-Travis Drift-Flux Controversy(T. A. Porsching)
Reply to “Comments on the Lyczkowski-Travis Drift-Flux Controversy”(Robert W. Lyczkowski)
Energy From Heaven and Earth(Alvin M. Weinberg)
Nuclear Safeguards Analysis(Clement J. Rodden)
Corrigendum: Neutron Streaming in LMFBR

A Numerical Study of Weakly Compressible Rotating Flows in a Gas Centrifuge

Iwao Harada

Nuclear Science and Engineering / Volume 73 / Number 3 / March 1980 / Pages 225-241

Technical Paper / dx.doi.org/10.13182/NSE80-A19848

The Effects of Sodium Entrainment and Heat Transfer with Two-Phase UO₂ During a Hypothetical Core Disruptive Accident

Michael L. Corradini, Warren M. Rohsenow, Neil E. Todreas

Nuclear Science and Engineering / Volume 73 / Number 3 / March 1980 / Pages 242-258

Technical Paper / dx.doi.org/10.13182/NSE80-A19849

Neutron and Gamma-Ray Penetrations in Thick Iron

Yoshiaki Oka, Shigehiro An, Shigeru Kasai, Shun-ichi Miyasaka, Kinji Koyama

Nuclear Science and Engineering / Volume 73 / Number 3 / March 1980 / Pages 259-273

Technical Paper / dx.doi.org/10.13182/NSE80-A19850

Homogenized Diffusion Approximations to the Neutron Transport Equation

Edward W. Larsen, R. P. Hughes

Nuclear Science and Engineering / Volume 73 / Number 3 / March 1980 / Pages 274-285

Technical Paper / dx.doi.org/10.13182/NSE80-A19851

Parameter Estimation of Liquid-Metal Fast Breeder Reactor Simulation Experiments Using Univariate Autoregressive Integrated Moving Average Modeling

M. I. Pekarsky, C. C. Meek, R. C. Doerner

Nuclear Science and Engineering / Volume 73 / Number 3 / March 1980 / Pages 286-289

Technical Note / dx.doi.org/10.13182/NSE80-A19852

Comments on Higher Order Generalized Perturbation Theory

A. Gandini

Nuclear Science and Engineering / Volume 73 / Number 3 / March 1980 / Pages 289-294

Technical Note / dx.doi.org/10.13182/NSE80-A19853

Multidimensional Space-Time Kinetics of a Heavy-Water-Moderated Nuclear Reactor

W. G. Winn, N. P. Baumann, C. E. Jewell

Nuclear Science and Engineering / Volume 73 / Number 3 / March 1980 / Pages 294-300

Technical Note / dx.doi.org/10.13182/NSE80-A19854