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