Home / Publications / Journals / Nuclear Science and Engineering / Volume 37 / Number 3

Volume 37

Number 3

Table of Contents
PIGG(T. Kulikowska, J. O. Berg, G. E. Fladmark, O. P. Tverbakk)
ETOX: A Code to Calculate Group Constants for Nuclear Reactor Calculations(R. E. Schenter, J. L. Baker, R. B. Kidman)
1DX: A One-Dimensional Cross Section Generating Code(R. W. Eardie, W. W. Little, Jr.)
NØWIG(J. B. Yasinsky)
Nuclear and Particle Physics(Robert W. Richardson)

Heat Conduction in Reactor Fuel Elements

G. Hetsroni, E. Wacholder, S. Haber

Nuclear Science and Engineering / Volume 37 / Number 3 / September 1969 / Pages 329-336

Technical Paper / dx.doi.org/10.13182/NSE69-A19109

Calculation of the Radiation Hazard at Supersonic Aircraft Altitudes Produced by an Energetic Solar Flare

T. W. Armstrong, R. G. Alsmiller, Jr., J. Barish

Nuclear Science and Engineering / Volume 37 / Number 3 / September 1969 / Pages 337-342

Technical Paper / dx.doi.org/10.13182/NSE69-A19110

Analysis of Neutron Focusing by Conical Tubes and its Possible Applications

T. Shimooke

Nuclear Science and Engineering / Volume 37 / Number 3 / September 1969 / Pages 343-357

Technical Paper / dx.doi.org/10.13182/NSE69-A19111

Neutron-Wave Propagation in Crystalline Moderators—IV: A Two-Group Study

Ashok Kumar, F. Ahmed, L. S. Kothari

Nuclear Science and Engineering / Volume 37 / Number 3 / September 1969 / Pages 358-367

Technical Paper / dx.doi.org/10.13182/NSE69-A19112

Slow-Neutron Scattering by Molecular Liquids

Ashok K. Agrawal, Sidney Yip

Nuclear Science and Engineering / Volume 37 / Number 3 / September 1969 / Pages 368-379

Technical Paper / dx.doi.org/10.13182/NSE69-A19113

Input-Noise Source of At-Power Reactors with Temperature Feedback Effect

Keiichi Saito

Nuclear Science and Engineering / Volume 37 / Number 3 / September 1969 / Pages 380-396

Technical Paper / dx.doi.org/10.13182/NSE69-A19114

Energy-Dependent Neutron Transport Theory Near a Temperature Discontinuity

Eugene C. Gritton, A. Leonard

Nuclear Science and Engineering / Volume 37 / Number 3 / September 1969 / Pages 397-409

Technical Paper / dx.doi.org/10.13182/NSE69-A19115

Monte Carlo Integration of the Adjoint Neutron Transport Equation

Bo Eriksson, Claes Johansson, Martin Leimdorfer, M. H. Kalos

Nuclear Science and Engineering / Volume 37 / Number 3 / September 1969 / Pages 410-422

Technical Paper / dx.doi.org/10.13182/NSE69-A19116

Space-Energy Flux Synthesis in Transport Theory

M. J. Lancefield

Nuclear Science and Engineering / Volume 37 / Number 3 / September 1969 / Pages 423-442

Technical Paper / dx.doi.org/10.13182/NSE69-A19117

Stabilizing Control Functions

Gary M. Sandquist

Nuclear Science and Engineering / Volume 37 / Number 3 / September 1969 / Pages 443-450

Technical Paper / dx.doi.org/10.13182/NSE69-A19118

Pressurized Water Reactor Optimal Core Management and Reactivity Profiles

Michel Mélice

Nuclear Science and Engineering / Volume 37 / Number 3 / September 1969 / Pages 451-477

Technical Paper / dx.doi.org/10.13182/NSE69-A19119

An Evaluation of the Activation Cross Section of ¹⁵¹Eu

F. V. Orestano, F. Pistella

Nuclear Science and Engineering / Volume 37 / Number 3 / September 1969 / Pages 478-480

Technical Note / dx.doi.org/10.13182/NSE69-A19120