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Volume 31

Number 1

Table of Contents
Proceedings of Symposium on Criticality Control of Fissile Materials(E. R. Woodcock)
Fast Reactor Technology: Plant Design(Eugene R. Astley)
Importance of The Adjoint Function(J. Wallace Webster)
Comment on Carlvik's Paper on Dancoff Correction in Lattices(P. J. Fulford)
On the Connection Between Absorption and Anisotropy of Scattering in Neutron Transport Theory(A. I. Usseli, P. F. Zweifel)
Virtual Limitation of Variational Principle(S. R. Dwivedi)

Drop Extraction Between Liquid Metals and Fused Salts

Donald R. Olander

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 1-18

Technical Paper / dx.doi.org/10.13182/NSE68-A18003

Experimental Studies of Microparameters of Clusters of Seven Nuclear Superheat Reactor Fuel Rods

J. T. Wajima, H. Yamamoto, H. Kikuchi, T. Ohnishi, S. Kobayashi

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 19-31

Technical Paper / dx.doi.org/10.13182/NSE68-A18004

Theoretical Analyses of Homogeneous Plutonium Critical Experiments

C. R. Richey

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 32-39

Technical Paper / dx.doi.org/10.13182/NSE68-A18005

Criticality of Heterogeneous Arrays Undergoing Dissolution

C. R. Richey

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 40-48

Technical Paper / dx.doi.org/10.13182/NSE68-A18006

Age Measurements in ThO₂-D₂O-H₂O Lattices

Donald M. Roberts, William G. Pettus

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 49-56

Technical Paper / dx.doi.org/10.13182/NSE68-A18007

A Comparison of Heterogeneous Nuclear-Reactor Lattice Theory with Experiment

W. E. Graves, F. D. Benton, R. M. Satterfield

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 57-66

Technical Paper / dx.doi.org/10.13182/NSE68-A18008

On the Stability of Nonlinear Space-Dependent Reactor Kinetics

William E. Kastenberg, Paul L. Chambré

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 67-79

Technical Paper / dx.doi.org/10.13182/NSE68-A18009

On the Use of Dual Variational Principles for the Estimation of Error in Approximate Solutions of Diffusion Problems

J. B. Yasinsky, S. Kaplan

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 80-90

Technical Paper / dx.doi.org/10.13182/NSE68-A18010

Flux Synthesis Using Green's Function in Two-Dimensional Group Diffusion Equations

Keisuke Kobayashi

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 91-101

Technical Paper / dx.doi.org/10.13182/NSE68-A18011

Neutron Thermalization in Heavy Gas with Nonuniform Temperature Distribution

Pekka Jauho, Antti Virjo

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 102-109

Technical Paper / dx.doi.org/10.13182/NSE68-A18012

Albedo and Milne's Problem for Thermal Neutrons

S. Pahor

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 110-116

Technical Paper / dx.doi.org/10.13182/NSE68-A18013

A Boltzmann Integral Equation Treatment of Neutron Resonance Absorption in Reactor Lattices

E. E. Lewis, F. T. Adler

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 117-126

Technical Paper / dx.doi.org/10.13182/NSE68-A18014

Transport Error Bounds Via P_N Approximations

James A. Davis

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 127-146

Technical Paper / dx.doi.org/10.13182/NSE68-A18015

A Study Concerning the Number of “Effective” Equally Limiting Hot Channels in a Reactor with a Cosine Power Distribution

F. D. Judge

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 147-148

Technical Note / dx.doi.org/10.13182/NSE68-A18016

Effects of Voids on Diffusion Length and Streaming of Neutrons in Water

Naeem Ahmad Khan, S. M. Kabir

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 148-149

Technical Note / dx.doi.org/10.13182/NSE68-A18017

Neutron Absorption Cross Section of ²³⁷U

W. R. Cornman, E. J. Hennelly, C. J. Banick

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 149-152

Technical Note / dx.doi.org/10.13182/NSE68-A18018

The Thermal-Neutron Capture Cross Section of Cadmium

J. W. Meadows

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 152-153

Technical Note / dx.doi.org/10.13182/NSE68-A18019

Neutron Spectra in Thin Polyethylene Slabs

S. B. Armstrong

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 153-155

Technical Note / dx.doi.org/10.13182/NSE68-A18020

Neglect of the Energy-Angle Correlation in Nonscattering Neutron Emission Reactions

S. T. Perkins

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 156-157

Technical Note / dx.doi.org/10.13182/NSE68-A18021

On Solving Certain Group-Diffusion Problems in Finite-Difference Form

Melvin Tobias

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 157-160

Technical Note / dx.doi.org/10.13182/NSE68-A18022

Time-Dependent Variational Theory

Jeffery Lewins

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 160-163

Technical Note / dx.doi.org/10.13182/NSE68-A18023

The Effect of Source Distribution on Neutron Resonance Integrals

A. C. deLoach and J. E. Suich

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 163-167

Technical Note / dx.doi.org/10.13182/NSE68-A18024

A Reformulation of the Doppler Effect in Resonant Neutron Capture

W. G. Pettus

Nuclear Science and Engineering / Volume 31 / Number 1 / January 1968 / Pages 168-169

Technical Note / dx.doi.org/10.13182/NSE68-A18025