Home / Publications / Journals / Nuclear Science and Engineering / Volume 71 / Number 2

Volume 71

Number 2

Table of Contents
On the Eigenvalues of the Stationary and Time-Dependent Boltzmann Equation in Its Integro-Differential and Integral Forms(V. Protopopescu)
Comments on “On the Eigenvalues of the Stationary and Time-Dependent Boltzmann Equation in Its Integro-Differential and Integral Forms”(N. G. Sjöstrand)
Nuclear Reactor Theory and Design(N. C. Francis)

Factorized Kernels and the DKPL Solution to the Third Form of the Neutron Transport Equation in a Rectangular Parallelepiped

A. Bassini, F. Premuda, W. A. Wassef

Nuclear Science and Engineering / Volume 71 / Number 2 / August 1979 / Pages 87-99

Technical Paper / dx.doi.org/10.13182/NSE79-A20401

Discrete Transfer Cross-Section Expansion for Time-Dependent Neutron Transport

F. Beranek, R. W. Conn

Nuclear Science and Engineering / Volume 71 / Number 2 / August 1979 / Pages 100-110

Technical Paper / dx.doi.org/10.13182/NSE79-A20402

Computational Efficiency of Numerical Methods for the Multigroup, Discrete-Ordinates Neutron Transport Equations: The Slab Geometry Case

R. E. Alcouffe, E. W. Larsen, W. F. Miller, Jr., B. R. Wienke

Nuclear Science and Engineering / Volume 71 / Number 2 / August 1979 / Pages 111-127

Technical Paper / dx.doi.org/10.13182/NSE71-111

Analysis of Error in Monte Carlo Transport Calculations

Thomas E. Booth, Edmond D. Cashwell

Nuclear Science and Engineering / Volume 71 / Number 2 / August 1979 / Pages 128-142

Technical Paper / dx.doi.org/10.13182/NSE79-A20404

Reactivity Measurements in a Thorium Critical Assembly

Keiji Kobayashi, Junnosuke Horie, Keiji Kanda, Toshikazu Shibata

Nuclear Science and Engineering / Volume 71 / Number 2 / August 1979 / Pages 143-153

Technical Paper / dx.doi.org/10.13182/NSE79-A20405

Critical Experiments with Lattices of 475-wt%-²³⁵U-Enriched UO₂ Rods in Water

J. C. Manaranche, D. Mangin, L. Maubert, G. Colomb, G. Poullot

Nuclear Science and Engineering / Volume 71 / Number 2 / August 1979 / Pages 154-163

Technical Paper / dx.doi.org/10.13182/NSE79-4

Effect of Soluble Neutron Absorbers on the Criticality of Low-Uranium-235 Enriched UO₂ Lattices

R. C. Lloyd, B. M. Durst, E. D. Clayton

Nuclear Science and Engineering / Volume 71 / Number 2 / August 1979 / Pages 164-169

Technical Paper / dx.doi.org/10.13182/NSE79-A20407

Characteristics of a Beam-Driven Deuterium-Fueled Fusion-Fission Reactor System

K. F. Schoepf, A. A. Harms

Nuclear Science and Engineering / Volume 71 / Number 2 / August 1979 / Pages 170-181

Technical Paper / dx.doi.org/10.13182/NSE79-A20408

^{104,105,106,108,110}Pd (n,γ) Cross Sections Above 2.6 keV

R. L. Macklin, J. Halperin, R. R. Winters

Nuclear Science and Engineering / Volume 71 / Number 2 / August 1979 / Pages 182-191

Technical Paper / dx.doi.org/10.13182/NSE79-A20409

Multiple-Jet Thermal Mixing in a Piping Tee

Paul S. Lykoudis, Robert C. Hagar

Nuclear Science and Engineering / Volume 71 / Number 2 / August 1979 / Pages 192-201

Technical Paper / dx.doi.org/10.13182/NSE79-A20410

Accuracy and Computational Time of a Hierarchy of Growth Rate Definitions for Breeder Reactor Fuel

P. J. Maudlin, R. C. Borg, K. O. Ott

Nuclear Science and Engineering / Volume 71 / Number 2 / August 1979 / Pages 202-205

Technical Note / dx.doi.org/10.13182/NSE79-A20411

⁶Li(n,α)T Cross Section from 70 to 3000 keV from the ²³⁵U(n,f) Calibration of a Thin Glass Scintillator

R. L. Macklin, R. W. Ingle, J. Halperin

Nuclear Science and Engineering / Volume 71 / Number 2 / August 1979 / Pages 205-208

Technical Note / dx.doi.org/10.13182/NSE79-A20412

The Energy Dependence of Fission Fragment Anisotropy in Fast-Neutron-Induced Fission of Uranium-235

S. Ahmad, M. M. Islam, A. H. Khan, M. Khaliquzzaman, M. Husain, M. A. Rahman

Nuclear Science and Engineering / Volume 71 / Number 2 / August 1979 / Pages 208-211

Technical Note / dx.doi.org/10.13182/NSE79-A20413

The Calculation of the Void Fraction by Slip Ratio Correlations: A General Method

F. Norelli

Nuclear Science and Engineering / Volume 71 / Number 2 / August 1979 / Pages 212-215

Technical Note / dx.doi.org/10.13182/NSE79-A20414

Thermal Radiation Properties of Interfaces Between Nuclear Reactor Materials

S. H. Chan, H. H. Tseng

Nuclear Science and Engineering / Volume 71 / Number 2 / August 1979 / Pages 215-227

Technical Note / dx.doi.org/10.13182/NSE79-A20415